ML20236F385
| ML20236F385 | |
| Person / Time | |
|---|---|
| Site: | 07105874 |
| Issue date: | 07/29/1987 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20236F371 | List: |
| References | |
| NUDOCS 8708030320 | |
| Download: ML20236F385 (6) | |
Text
T I
l gas mansmax wa sa mma mmm mmm am a xxmma sam man -m a xmmma nnwam ma sa s.y N~.C FORM 61:
U.S. NUCLEAR REGULATORY COMMISSION 4
+asi CERTIFICATE OF COMPLIANCE g
to cFR 7' FOR RADIOACTIVE MATERIALS PACKAGES i
b REVISION NUM85R C PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES f
a CERTIFICATE NUMBER 5874 5
USA /5874/B( )F 1
3 l
[4 2 pAEaMetE a This certificate is issued to c ertsf y that the packa2'ng and cor cents cescribed in item 5 below, meets the appheabas cafety standards set fortn in Title 10. Code of Federal Regulations Part 71. " Packaging and Transportation of Radioactwe Material '
b This certificate does not relieve the consignor from complia9ce with any requirernent of the regulations of the U S. Department of Transportation or other apphCable regulatory agencies including the government Of any Country tnrougn or into which the package wdl be transported l
a
'o T LE AND IDE F CAflON OF EPOR O AP IC A TION s
D7
.A i
l Department of Energy Safety Analysis for Radioactive Material l
I Division of Naval Reactors Shipping Cask No. WAPD-40 dated Washington, DC 20585 December 1984, as supplemented.
l 71-5874 c DOcxET NuvaEa i4 cONOifiONS I
This certificate is conditional upon fo f ahng the requirements of to CFR Part 71 as apphcable. and the conditions specified below 3
i r
6 t
l (a) Packaging l
(1) Model No.: WAPD-40 l
l 1
4 (2) Description j
l
,i The PAPD-40 shipping container is a cylindrical, stainless steel i
g clad, lead shielded, shipping container used to ship irradiated fuel 1
k and non-fuel test specimens. The container has an outer Type 304 W(l stainless steel shell 1/2-inch thick and an inner Type 304 stainless l
steel shell 1/4-inch thick, with 9.875 inches of lead between the f
shells. The overall size of the container, including an integral i
skid, is 23.25 inches in diameter by 158 inches in length.
Gross ll l
gl weight (including skid) of the container is approximately 28,000 q
a pounds. The heat removal capacity is approximately 2000 BTV/ hour.
W The cylindrical inner cavity is 2 inches in diameter and 135 inches i3 8,
in length.
Inner containers are required for all shipments.
l'
(
Stainless steel clad, lead shielded end plugs bolt into each end.
qli One-half inch thick plates are bolted over the end plugs to provide g
a total end plug flange thickness of 1.0 inch for puncture g
resistance. Metallic, pressure-filled 0-rings between the end plugs
%l and the container seal the package.
The cask may be wrapped in l1 8
polyvinyl chloride when shipped in a closed truck. A special i'
l holddown cradle is used during truck shipments.
This cradle weighs I
approximately 5,000 pounds.
q, (3) Drawings l
4
[f N
The WAPD-40 cask is fabricated in accordance with Westinghouse Assembly Drawing Nos. 936F577, Rev. 11; and 936F578, Sheet 1, f
Rev. 9, and Sheet 2, Rev. 4.
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I 870B030320 070729 i
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PDR I
wmmmm-== = - - - - = = - - - - --m um m-mmmmmmm=== mmmm - - = - - - - - - i=> mm mmmr I
l CONDITIONS (continutd) l Page 2 - Certificate No. 5874 - Revision No. 5 - Docket No. 71-5874 I
I I
5.
(b) Contents l
I (1) Type and form of material l
l Byproduct and special nuclear material contained within inner i
product containers. The contents must be dry and unmoderated (H to I
X atomic ratio <, 2).
I I
(2) Maximum quantity of material per package l
The fissile content of the cask must be limited to a maximum of 350 i
equivalent grams of U-235.
The number of equivalent grams of U-235 I
is determined by the equation:
1.0 x grams U-235 + 1.4 x grams i
U-233 + 1.6 x grams plutonium.-
s l
l (c) Fissile Class II l
Minimum transport index to be shown on label 3.2 i
5 6.
Maximum decay heat per package must not exceed 2,000 BTU /hr.
4 8
7.
As needed, shoring must be used to limit movement of contents under accident l
conditions of transport.
l 8.
The lifting trunnions must be covered during transport to preclude their use s
as tie-down devices.
1 4
9.
The contents of the container must be limited so that the maximum measured f
gamma dose rate (above background) on the side of the cask for normal j
conditions does not exceed the value defined by C3 = (1000-N )/F.
A 6
(
where C the maximum permissible gamma dose rate on the side 3 = of the cask in mrem / hour for normal conditions.
4 N
NA = ma.0 mrem / hour for shipments of irradiated sturctural 0
f-terials and 37.0 mrem / hour for shipments of irradiated fuel.
4 W
F = factor obtained directly from Table 1 or Table 2 (attached).
M 8
For non-fuel whose principal isotope is not included in Table 1, an F factor l
l must be determined based on calculated ratios of the limiting accident y
radiation levels to the normal condition radiation levels for each of the 3_
principal isotopes.
233 For U withapproximately30,000hoursofeffectivefullpoweroperaggn j
and greater than 17,520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br /> of decay, the F factors in Table 2 for V l
g are conservative and may be used.
l h
The maximum measured neutron level dose rate on the side of the cask must 4
not exceed 10.7 mrem / hour for normal conditions.
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w - - -, - - - - m m m - m m,.s_, _ _ _ _
m.- - - _ - _ _ _ _ _ _ ; ;,.- - _ _ _,,-r_
I s
CONolTIONS (continurd)
,)
I I
Page 3 - Certificate No. 5874 - Revision No. 5 - Docket No. 71-5874 ji I
I I
I 9.
Continued
!l l
l ljll I
For mixed shipments of fuel and irradiated non-fuel, the more limiting C 3 I
value must be employed, l
!l If C is below the maximum measurable level of the gamma instrument, other g
l methods (e.g., thermal luminescent detectors, source strength calculations) lg I
must be employed to estimate the expected level for comparison with C.
l 3
I i
I
- 10. The acceptance tests and maintenance program must be in accordance with I
l Chapter 8.0 to WAPD-RE0(C)-270, Rev. 3.
Nj l
i i
- 11. The WAPD-40 shipping container may be covered with a wrapping of polyvinyl jy l
chloride (PVC) during shipment provided that the internal heat load of the lg I
shipment does not exceed 2000; BTU /hr and the shipment is made in a closed
- p I
truck.
The applicable requirements of Condition'No. 9 above must be satisfied jN l
prior to wrapping.
N l
- 12. Expiration date: July 31, 1992.
r,!
4 REFERENCES
!i
(
l Safety Analysis for Radioactive Material Shipping Cask No. NRBK-40 dated g
December 1984 (WAPD-RE0(C)-270, through Rev. No. 4).
4l Naval Reactors supplements dated: July 3, 1985'(S#85-1328), and May 6, 1987 l f (S#.87-2721)
- p I
y 1,
1 FOR THE U.S. NUCLEAR REGULATORY COMMISSION
- R i
bA l
Charles E. MacDonald, Chief j !
Transportation Branch i
Division Safeguards and ly Transportation, NMSS y
l 4
JUL 2 91967 y
a Date:
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i-Attachment to USA /5874/B( )F Rev. 5 Page 1 Table 1 l
F Factors For Use in Formula C3=(1000-N)/F A
For Irradiated Structural Material Shipments by Principal Isotope Isotope Energy and Yield Factor MeV
([/ decay)
. Manganese-56 0.47 0.99 174 1.81 0.29 2.11
.0.15 Cobalt-60 1.17 1.0 1492 1.33 1.0 Iron 1.095 0.56 1875 1.292 0.44 IThe F factor is a constant for each isotope because the energy spectrum of the emitted gamma radiation of each isotope does not change as a function of tine.
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UNITED STATES n
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NUCLEAR REGULATORY COMMISSION
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E wAsmNGTON, D. C. 20655 0
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U.S. Department of Energy Division of Naval Reactors Docket No. 5874 I
By application dated May 6, 1987, the U.S. Department of Energy requested that Certificate No. 5874 be amended to allow the WAPD-40 shipping package to be wrapped in a polyvinyl chloride (PVC) cover to reduce the spread of contamination during shipment. The amendment would also require that shipment of the covered WAPD-40 package be made in a closed truck.
In addition, the amendment proposed several minor changes in the package's description.
1 The major effect of the PVC covering is to create an additional temperature drop (thermal barrier) in the gap between the package and the surrounding PVC wrapping resulting in a higher package temperature under normal transport conditions. Shipping the package in a closed truck would also increase the ambient temperature surrounding the package. However, the applicant has J
demonstrated that the higher temperatures predicted for the wrapped package l
under normal conditions do not exceed those previously predicted in the August 1981 SARP (WAPD-RE0(C)-270) for the unwrapped package.
This is because j
the results of the 1981 SARP were based upon an ambient temperature requirement 1
of 130*F; Part 71 has since been revised to require an ambient temperature of 100*F. Because the pre-fire temperatures in the 1981 SARP are greater than those predicted for the PVC wrapped package, the hypothetical fire accident analysis in the 1981 SARP was used to evaluate the fire accident condition.for l
the PVC-Wrapped WARP-40 package in a closed truck.
The 1981 SARP indicated that lead melted in the shielding during hypothetical l
fire accident conditions. As a result, limitations have been placed on the l
allowable measured dose rates at the package's surface for normal conditions l
(See Condition 9. Revision 5). The approval has been conditioned to assure l
that these dose rates are measured prior to the package being wrapped for l
shipment.
i l
The changes proposed in the package's description were to clarify certain of l
the package's dimensions and have no effect on the package's ability to meet 10 CFR 71.
The proposed amendment as conditioned meets the requirements of 10 CFR 71.
W ffx-u Charles E. MacDonald, Chief Transportation Branch Division of Safeguards and Transportation, NMSS Date:
1
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