ML20132F464
| ML20132F464 | |
| Person / Time | |
|---|---|
| Site: | 07105874 |
| Issue date: | 07/03/1985 |
| From: | Engel W ENERGY, DEPT. OF |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 25480, NUDOCS 8507180455 | |
| Download: ML20132F464 (8) | |
Text
-,
7p 5279 Phf afm f, s
Department of Ener JG.-5 D 19 MU Washington, D.C. 2 85 NR:RM:PJWindley St85-1328 July 3, 1985 C. E. MacDonald Chief, Transportation Certification Branch Nuclear Regulatory Commission Washington, D.
C.
20555 WAPD-40 SHIPPING CONTAINER FOR IRRADIATION TEST SPECIMENS - DOE CERTIFICATE OF COMPLIANCE; FORWARDING FOR INFORMATION Nuclear. Regulatory Commission (NRC) memorandum FCTC: RHO 71-5874 dated May 31, 1985 forwarded the NRC Certificate of Compliance for the WAPD-40' shipping container.
Naval Reactors has issued a DOE Certificate of Compliance for the WAPD-40 shipping container.
The new DOE certificate has been modified to delete unneeded references to outside documents and drawings and now references only the Safety Analysis Report for Packaging (SARP) and the WAPD-40 drawings.
The list of inner container drawings has been deleted.
The list of approved inner containers will be maintained separately by Bettis Atomic Power Laboratory.
Further, the certificate allows the methods used to calculate thg3ga mum p rm ssa e ra ggjn ee n
e a
s side for a U cargo to be used for U cargoes as well.
A copy of the DOE certificate is attached as Enclosure (1).
Enclosure indicates that use of the $35" cargo *es"as w* ell as U*bbb"rgoe".
(2) conservative when applied to U ca s
NR evaluation has concluded that these changes do not affect compliance of the WAPD-40 shipping container with 10 CFR 71.
It is requested that a revised NRC certificate of compliance for this container consistent with enclosure (1) be forwarded.
[
g
/
00curm
/
W.
P.
GEL 7
WC Naval Reactors 1
-2
+
uuL 3 m33 y)9 z
A w,
Enclosures:
(1)
Department of Energy Certificate 'ofsCodipl'iand:e /8/
Rev. 3 dathd Jult"l'
'985 USA /5874/B(g (DOE-NR),
(2)
Table for U Shipments
/ ;g CC:
C. E. MacDonald (NRC) 2 copies with enclosure R. Garrison, DOE (w/o enclosure)
Manager, PNRO (w/o enclosure)
Manager, Shipping Container Analysis, Bettis (w/o enclosure) f b
or L
re-..'
'y l
._ j J
s K
i..
t..,
r
~
~ DOCKET NO.
~ 2 /-- N 2
.u
- o CONTROL NO.
'12[fhb
^
'oATa ai noc._ b7/03/25 d'77#/hI^
DATE RCVD.
- r f
FCUT*
PDF. '
/
FCAF LfDR W
ISE REF, s/
^
WUR SAFRGUARDS PCTC_
OTH R nachimox:
z W
W s$amaa L l L.' Y $l' 24fM
.(D#6sikctuuw M 7
e t
'y r
.\\
.i w,
U.S. DEPARTMENT OF ENERGY OMB Approval CERTIFICATE OF COMPLlANCE DOE F 5:211 No 1910 2000 45 85)
For Radioactive Materials Packages (Formerly EV 618)
I ic. Package identification No.
Id. Page No.
Ie. Total No. Pages 1b. Revi6 ion No.
la Certificate Number USA /5974/BI )F (1YF-NR1 1
4 IEA/5874/B( )F (DOE-NR) 1 3
- 2. PREAMBLE This certificate is issued under the authority of 49CFR Part 173.7 (d).
2a.
The packaging and contents described in item 5 below, meets the safety standards set forth in sub Standards" and subpart F," Package and Special Form Tests" Title 10, Code of Federal Regulatiqns 2b.
This certificate does not relieve the consignor from compflance with any requirement of the regulations of Transportation or other applicable regulatory agencies, including the government of any country through 2C.
Dackage will be transported.
- 3. This certificate is issued on the basis of a safety analysis report of the package design or application-(3) Date-(2) Title and identification of report or application:
(1) Pr: pared by (Name and address 1:
Safety Analysis Report for August 1991 Bettis Atomic Power Laboratory Packaging for the M PD-40 P. O. Box 79 Pittsburgh, PA 15122-0079 Shipping Container (2PD-RD3(C)-270 dated Atgust,1981 as revised)
Attn Mgr., Shipping Container Analysis This certifica'e is conditional upon the fulfitting of the applicable Operational and Quality Assurance requ
- 4. CONDITIONS 100199 and 10CFR Part 71, and the conditions specified in elem 5 below.
- 5. Description of Packaging and Authorized Contents. Model Number. Fissile Class. Other Conditions MPD-40 Radioactive Materials Shipping Container c.
==
Description:==
The MPD-40 shipping container is an cylirrirical, stainless steel clad, lead shielded, shipping container used to ship irradiated fuel and ncn-fuel test specimens. The container has an outer 304L stainless steel shell 1/2-inch thick and an inner 304L stainless t
steel shell 1/4-inch thick, with 10 inches of lead between the shells. The overall size of the container, including an integral Gross skid, is 24 inches in diameter by 168 inches in length.
weight (including skid) of the container is approximately 27,500 The heat removal mpacity is approximately 2000 BTU /hr.
pounds.
The cylindrical inner cavity is 2 inches in diameter and 135 inches in length. Inner crntainers are required for all shipments, (see Item 5.c.(4), below). Stainless steel clad, lead shielded end plugs One-half inch thick plates are bolted over the bolt into each end.
end plugs to provide a total end plug flange thickness of 1.0 inch for puncture resistance. Metallic, pressure-filled o-rings between the end plugs aryl the container seal the package. A special This cradle weighs holMown cradle is used during truck shipments.
l at E=oiretion Dete August 31, 1990 h Date of teswaee July 1, 1985 FOR THE U $_. der ARTMENT OF ENERGY 7ti. s.eneiure, Nemo, and Taie jer cot Aapro,,ne arr,e,,q 7e. Aesroes Ier oct isewas ort,ees S_, 0 W'/ -
d Naval Reactors C. H. SONITT Department of Energy Deputy Director Washington, D.C.
% ha1 h e+rw e 90;As
tW5874/C( )F (DOE-NR), Rev. 3 Page 2 c.
(continued) approximately 5,000 pounds. The shipping container is cxmstructed in accordance with the following Westinghouse Electric Drawings:
MPD-40 Cask Assembly 936F577 (latest revision)
NED-40 Cask Details 936F578 (latest revision) b.
Authorized Centents The authorized contents of the package ocnsist of fissile and highway route controlled quantities of radioactive isotopic materials (including activated structural material, corrosicn products, and mixed fissian products) Which shall be contained in inner mntainers.
Since the container contents must be less than 350 equivalent grams of U-235 (see Item 5.c.(1) below) it is approved as a Fissile Class II container with a minimum Transport Index of 3.2 c.
Restricticms shipping container shal& be limited to 350 The fissile content og3pWhere the number of ecglent grams of (1)
Ugvalent grams of Uis determined by the equation: 1 x grams U
+ 1.4 x grams of e
U233 + 1.6 x grams of plutcnium.
(2) The decay heat limit of the cargo being shipped is 200 BTU / hour / foot, up to a total of 2000 BTU / hour.
(3) All shipments must be dry and unmoderated.
(4) The radioactive contents of the package must be contained in approved, sealed inner containers. A list of approved inner containers is available from Manager, Shipping Container Analysis, Bettis Atcmic Power Laboratory (See address in Item 3.(1) above).
During shipnent, the inner cavity of the cask must be completely filled with inner containers, even if some of these inner containers are empty.
(5) For ferrous alloys, inconel, and irradiated fuel, the ccntents of the container must be limited so that the maximum measured gamma dose rate (above background) cm the side of the cask for normal conditions does not exceed the value defined by Cg = (1000-N )/F.
A Where C3 = the maximum missible gama dose rate cm the side of the cask in mr hour for normal conditions.
A = 00.0 mrem / hour for shipments of irradiated structural N
materials and 37.0 mres/ hour for shipments of irradiated fuel.
USA /5874/B()F(DOE-NR),Rev.3 Pge3 c.
(continued)
F = factor obtained directly from Table 1 or Table 2.
These tables are provided as attachments to this rh,= ant.
For non-fuel Whose principal isotope is not included in Table 1, an F factor aust be determined based cm calculated ratios of the limiting accident radiation levels to the normal condition radiation levels for each of the principal isotopes.
Fcr U233 with approximately 30,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of effective full power Table 2 for U gester than 17,520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br /> of demy, the F factors in operation and2 are ocmsorvative and may be used.
The maximum measured neutron level dose rate cm the side of the cask must not exceed 10.7 mrom/ hour for normal conditions.
For mixed shipments of fuel and irradiated ncm-fuel, the more limiting C3 value must be employed.
If C is below the minimum measurable level of the gamma instrument, g
other methods (e.g., thermal luminescent detectors, source strength calculations) must be employed to estimate the expected level for comparison with C.
3 (6) Use of the trunnions for cask tiedown is prohibited.
The cask must be tested for leaktightness withigone yeag/ prior to (7)
Leaktightness is defined as leaka3e of 10~ atm-cm sec or use.
less.
(8) Prior to each shipment, the cask must be leak tested afpr 3
assembly. Acceptable leakage for this test will be 10~ atarcsn /,,e or less.
d.
References WD-RB0(C)-270 dated August 1981 as revised, Safety Analysis Report for Packaging for the Shipment of the WD-40 Shipping Container.
c.
Additional Informaticm See Attachment (2 pages)
Attadiment to IBA/5874/B( )F (DOE-NR), Rev. 3 Page 1 Table 1 F Factors 1 For Use in Fornila Cg = (Img)/F For Irradiated Structural Material Shipments by Principal Isotope Isiotope Energy and Yield Factor MeV (r/ decay)
Manganese-56 0.47 0.99 174 1.81 0.29 2.11 0.15 Cobalt-60 1.17 10 1492 1.33 1.0 Iron-59 1.095 0.56 1875 1.292 0.44 h F factor is a constant for each isotope because the energy spectrum of the emitted gama radiation of endt isotope does not change as a function of time.
c, Attachment to USA /5874/B( )F (DOE-tEt), Rev. 3 Page 2 Table 2 F Factors For Use in F
= (1000 g )/F For Irradiated Fuel ipments Effective Hours Full Power Hours Decay Operaticrt 720 1440 2160 4320 6480 8760 17,520 43,800 87,600 100 339 339 330 219 200 194 192 208 698 500 338 338 325 219 203 198 198 237 648 1000 338 337 318 219 206 203 206 268 629 5000 332 317 283 230 228 229 250 382 606 10,000 317 300 271 242 243 248 278 427 607 15,000 310 294 269 249 253 258 292 445 610 20,000 306 290 268 254 257 265 300 457 612 25,000 302 286 268 256 260 267 305 464 617 30,000 300 285 267 257 263 270 300 466 624 40,000 295 282 266 258 264 271 310 472 637 50,000 292 279 265 259 264 272 311 472 651 (DC5874 - 20D i
(.
Enclo;uro (2) to S#85-1328 o
SHIELDING EVALUATION - Support Information Thefollowinggggormationisprovidedtoshowthattheshielding analysis for U inadamagedgggD-40shippingcontaineris conservative for the proposed U contents.
The results in the table represent thI38' fuel as compared with irradiated UI3t
"*e*"a'tl i"9 fr "
- " "9'
""S*
L irradiated U fu l approximately 30,000 effective full power hours of operation.
CHANGE IN RADIATION LEVEL Hours Decay 24,000 43,800 87,600 Normal Conditions
-13.5%
-13.0%
-9.0%
Accident Conditions
-11.0%
-10.0%
-7.0%
Basedontheabovegggle,useoftheFPgggorsintheDOEcertificate of compliance for U fuel as well as U fuel is conservative.
I
\\
.