ML19290C121
| ML19290C121 | |
| Person / Time | |
|---|---|
| Site: | 07109069 |
| Issue date: | 09/19/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19290C116 | List: |
| References | |
| NUDOCS 8001090508 | |
| Download: ML19290C121 (5) | |
Text
l y
ATTACHMENT II s.\\
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U.S. NUCLE AR HLGUL atony COMMISSION CERTIFICATE Or c0Mi>LI ANcE
/[
For Radinactive Materials Packars f
1.f el Pack 7 1.(d ) Pages No. 1.(e) T: tal '.s. 9,.
N U3A/5450'e M niification No.
1.(b) Revision No.
1.la) 54"6F caf e FJumber 6
/8
)F 1
5 0
- 2. PREAMBLE 173.3333,173.'"14,173.395, and 173.30G of the Ocpartment of Trantrrrtwar: hs:
2 ::.
2.(a)
This certificate is issu=J to sati fy Ecctions fAaterials Ftegulations (43 CFft 170-1E9 ami 14 CFH 103) and Sections 14G-19-10a and 146-19-100 of the Depcrtment of Transpartstion Dangerous Cargoes Regulations (46 CFR 14C-149), as amended.
The fuckming and contents described in item 5 tclow, meets the safety standarcis set forth in Subpart C of Title 10. Ccde of 2.fb)
Federal Re.;ulations, Part 71, **Packajing of etacoactive f/aterials for Teansport and Transportation of Radioa:dve t/aterial U.w Certain Cc,nditions."
2.(c)
This certificate does not relieve the consignor from compliance with any rrquirement of the regulations of the U.S. Departrrent cf Transportatior. or other applict.ble regulatory agencies, including the government of any country through or into which the p2ces;*
will be tran: ported.
- 3. This certific.te is itsued on th? ba:is of a safety analysis report of the packa,e design or application-3.(a)
Preparc<f by (Name and address):
3.(b)
Title and identification of report or application:
Westinghouse Electric Corporation Westinghouse Electric Corporation application i
P.O. Box 355 dated July 13, 1973, as supplemented l
Pittsburgh, PA 15230 71-5450 3.(c)
Docket No.
4
- 4. CONOf flONS This certificate is conditic,nal upon the fulfi!!ing of the rcauirements of Subpart D of 10 CFR 71, as epplicable, and the conditions sce:!f:sd i
l In item 5 below.
- 5. De:cription of Face:gir.g and Authorind Contents, Madcl (Jumber Fissile Class, Other Corditions, and Rcierences:
l (a)
Packaging i
j (1) Madels Nos.:
RCC, RCC-1, RCC-2, and RCC-3 i
y
~
(2)
Description Steel fuel element cradle assembly consisting of a strongback and adjustatie fuel element clamping assembly, shock mounted to a 14-gage steel outer container by shear mounts.
Neutron absorber plates are required for the contents as specified.
(3)
Drawings Containers constructed in accordance with Westi.ighouse Electric Corporation Drcwings Nos. EDSK319401F, EDSK319402F, EDSK3231333, 684J580, for the RCC, 541F351, 6S4J861, 684J893, for the RCC-1, and 684J963, 541F614 and EDSK3231333 for the RCC-2, and 1215E34, 1213E59,1215E60,1464F14 for the RCC-3.
(4)
Fuel rod container reinforced 13-gage steel box approxicately 9"x9"xlG0" constructed in accordance with Westinghouse Electric CorporationDrawingNo.C56575.
i 1728 227 l
8 0 01000 [Q 8
7 f./
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ATTACHMENT.II
- /,
_oge 2 - Certificate !!o. 5450 - Revision flo. 6 - Docket f:o. 71-5450 5.
(b) Contents (1) Type and form of material (i) Uranium dioxide as zircaloy or stainless steel clad unirradiated fuel elements of the folloviing specifications:
15 x 15 14 x 14 14 x 14 15 x 15 Type Zr Clad Zr Clad SST Clad SST ' Clad Pellet diameter (ltom), in 0.367 0.367 0.384 0.384 Rod diameter (!!om), in 0.422 0.422 0.422 0.422 Maximum Fuel Length, in 144 144 120 122 Maximum Rods / element 204 180 180 204 Maximum Cross Sec+ ion (fiom),
in. sq.
8.4 7.8 7.8 8.4 Maximum U-235/ element, kgs 15 16 18 20 Maximum U-235/ enrichment, w/o 3.2 3.7 3.9 3.7 (ii) Uranium dioxide as zircaloy or stainless steel clad unir-radiated fuel elements.
Two (2) neutron absorber plates consisting of 0.19" thick, full length stainless steel containing 1.3% minimum boron or 0.19" thick 0FHC copper are required between fuel elements of the following specifications:
y 14x14 15x15 14x14 15x15 17x17 ilxll 15xiE Zr Zr SST SST Zr SST Zr Type Clad Clad Clad Clad Clad Clad Cla-Pellet diameter (iiom),
0.367 0.357 0.384 0.384 0.308-0.322 0.503
- 0. 3 E in Rod diameter (itom), in 0.422 0.422 0.422 0.422 0.360-0.374 0.567 0.372 Maximum Fuel Length, in 144 144 120 120 144 65.7 1." 2 Maximum Rods / element 180 204 180 204 264*
117 23E
!.'aximum Cross Section (f!om), in. sq.
7.8 8.4 7.8 8.4 8.4 8.7 7.E Maximum U-235/ element, kgs 17 18 18.5 20.5 16.25 9.3 la.E Maximum U-235 enrich-ment,w/o 3.85 3.59 4.0 4.0 3.5 4.3 3.5
- Cuide thimbles to be as shown in Figure 1 of application dated February 5,1974 for the 3.5 w/o enriched UO fuel and Figure 1 of application dated June 29, 1978 for i
2 fuel.
the 3.25 w/o enriched UO2 1728 228
~==.eswo m ~~ *- me r.. e.... w e...v e. - e.- -*.ew. e-s- --~e
~ w ~ee=.-~
~~, e e em m
.=a.-e.--~w e-
.w.m.s.~,,-,,-s
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ATTACHMENT II 71-5450
,sge 3 - Certificate flo. 5450 - Revision !!o. 6 - Docket No.
5.
(b)
Contents (continued)
(1) Type and form of material (continued)
Uranium dioxide as zircaloy or stainless steel clad (iii) unirradiated fuel rods of the following specifications:
Type SST Clad _
ZR Clad Zr Clad Pellet diameter (!!om), in 0.384 0.367 0.322 Rod dia.neter (iiom), in 0.422 0.422 0.374 Fuel length (!bx), in 144 144 144 Maximum U-235 enrichment, w/o 3.9 3.7 3.5 in natural UO2 as pressed sintered pellets fully (iv) Mixed Pu02 clad in leak-tight zircaloy of minimum 0.018" thickness as fuel rods which are asscmbled into fuel elements. Two (2) neutron absorber plates consisting of 0.19" thick, full length stainless steel containing 1.3% minimum boron or 0.19" thick, full length 0FHC copper are required betwcen fuel elez.ents of the following specifications:
q 14 x 14 Tyfe Pdllet diameter (!:en), in 0.367 0.429 Rod diameter (l'om), in 120 Maximum Fuel Length, in 180 Maximum Rods / element Mi.ximum Cross Section (!:om), in.sq.
7.8 14.5 Maximum Pu/ elements, kgs Maximum Pu fissile / element, w/o 3.31 in natural UO2 as pressed sintered pellets (v) Mixed pug 2 fully clad in leak-tight zircaloy of minimum 0.018" thickness as fuel rods of the following specifications:
Type 0.367 Pellet diameter (I!om), in 0.422 Rod. diameter (itom), in Fuel length (Hom), in 120 to 144 3.6 Highest w/o Pu fissile (!om) w/o 1728 229
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1/
ATTACHMENT II 0
. E ' J3 - Dreisicn ib. 6 - Dachtt ib. 71-5G
..;9e 4 - C.rtificate I:
5.
(b) Contents (Continued)
Maximum quantity of material per package (2)
For the contents described in 5(b)(1)(i) or (5)(b (i)
Two fuel elements.
(ii) For the contents described in 5(b)(1)(iii):
Two inner containers described in 5(a)(4) containing not mo than 66 kilograms U-235.
(iii) For the contents described in 5(b)(1)(iv):
Two fuel elements.
(iv) For the contents described in 5(b)(1)(v):
Two inner containers described in 5(a)(4) containing not more than 66 kilograms Pu.
II and III (c) Fissile Class Minimum transport index to be 1.5 (1) shown on label for Class 1.
v Maximum number of packages per 60 (2) shipment for Class III o more than Fuel rods shall be closely packed in the fuel rod container on nPartial an equivalent metal-to-metal square lattice.
lly spaced blocks, 6.
containers shall be fitted with a minimum of three, equa thod by which of which the nonccmbustible portion of the block more than fuel rod container.
an equivalent metal-to-metal square lattice within the in an unsealed, Each fuel assembly shall be uncheathed or shall be enclosed d
f the fuel polyethylene sheath which will not extend beyond the e 7.
h h athed fuel that would prevent the flow of liquids into or out of t e s e assembly.
assembly.
M l728 230
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ATTACHMENT II
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$ i ion flo. 6 Docket No.
i
- [e 5 Certificate flo. 5450 P v s losed in an clongated plastic l
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At the botton end of the fuel assemb y, Alternatively, the fuel assembly may be enc k to assure that the entire cross When folding is bag or sheath along its full length.
l bly is unobstructed.
f tape the bag will be cut off or folded bacsection of the low d the length will be such that w the d in used, the portion of the sheath that the folded sheath will be clampeTh h ed l
near its end to hold it in place, an lit on all assembly is loadec in the packaging, place in at le r
ing j
together and taped closed.The slits will run perpendicular tobetween th th of each side). top of the pads and clam and will extend the inner distance four sides.
clamps (approximately 60; of the lengmade in a pla d
h i i ns of Paragraph 71.12(b) o i
The package authorized by this Certif cafor use
., 8.
July 31,1930.
Expiration date:
REFERENCES 9
13, 1973, requesting t in the tion dated July Westinghouse Electric Corporation appl camaterial to a c i
approval to deliver special nuclear March 19,1975 1976; l
above packages.
Supple $ents dated February 5,1974;
- ffice, 29, 1978.
i tration, Richland Operations O August 2,1977; and June for ired only for the use of the package)(1)(ii) and Energy Research and Development Admin s l d fuel elements described in 5(b 16,1976 requ application dated Julythe shipment of the 11 x 11 SST c a FOR THE U.S. NUCLEAR SION limited in 5(b)(2)(i).
h $ ldcu (
Charles E. MacDonald, Chief Transportation BranchDivision of F Material Safety Date:
1728 231