ML20038A542
| ML20038A542 | |
| Person / Time | |
|---|---|
| Site: | 07105450 |
| Issue date: | 10/28/1981 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20038A541 | List: |
| References | |
| NUDOCS 8111130076 | |
| Download: ML20038A542 (5) | |
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Form NRC418 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE 10 C R 71 For Radioactive Materials Packages 1.(a) Certificate er 1.(b) Revision No.
1.(
a d
fication No.
1.(d) Pages No. 1.(e) Total Ng. Pages
- 2. PRE AMBLE 2.(a)
This certificate is issued to satisfy Sections 173.393a,173.394,173.395, and 173.396 of the Department of Transportation Hazardous Materials Regulations (49 CFR 170-189 and 14 CFR 103) and Sections 146-19-10a and 146--19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149), as amended.
2.(b)
The packaging and contents described in item 5 below, meets the safety standards set forth in Subpart C of Title 10 Code of Federal Regulations, Part 71," Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions."
2.(c)
This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other applicable regulatory agencies, including the government of any country through or into which the package will be transported.
- 3. This certificate is issued on the basis of a safety analysis report of the package design or application-3.(a)
Prepared by (Name and address):
3.(b)
Title and identification of report or application:
Westinghouse Electric Corporation Westinghouse Electric Corporation application-P.O. Box 355 dated December 17, 1980, as supplemented.
Pittsburgh, PA 15230 3.(c)
Docket No.
- 4. CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart D of 10 CFR 71, as app:icable, and the conditions specified in item 5 below.
- 5. Description of Packaging and Authorized Contents, Model Number, Fissile Class, Other Conditions, and
References:
(a)
Packaging (1) Model Nos.:
RCC, RCC-1, RCC-2, RCC-3, and RCC-4.
(2) Description Steel fuel element cradle assembly consisting of a strongback and adjustable. 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.
Gross weight for the RCC and RCC-2 is 6,300 lbs., RCC-1 and 2
RCC-3 is 7,200 lbs., and RCC-4 is 8,400 lbs.
(3) Drawings The packaging is constructed in accordance with Westinghouse Electric Corporation Drawing Nos.:
15%E24,1596E25, and 1553E30 for the RCC and RCC-3; 1596E24,1596E25, and 1553E31 for the RCC-1 and RCC-2; and 1596E22,1596E23, and 1548E55 for the RCC-4.
(4) Fuel rod container reinforced 13-gage steel box constructed in accordance with Westinghouse Electric Corporation Drawing No. C56J0055.
8111130076 811028 PDR ADOCK 07105 C
Page 2 - Certificate No. 5450 - Revision No.14 Docket No. 71-5450 5.
(b)
Contents (1) Type and form of material (1) Uranium dioxide as zircaloy or stainless steel clad unirradiated 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:
14x14 15x15 14x14 15x15 17x17 16x16 14x14 Zr Zr SST SST Zr Zr Zr Type Clad Clad Clad Clad Clad Clad Clad Pellet diameter 0.344-(nom),in 0.367 0.367 0.384 0.384 0.308-0.322 0.322 0.3805 R.,d diameter 0.400-(nom),in 0.422 0.422 0.422 0.422 0.360-0.374 0.374 0.44 Maximum fuel length, in 144 144 120 120 168 144 144 Maximum rods /
element 180 204 180 204 264 235 176 Maximum cross
- section, (nom),insq 7.8 8.4 7.8 8.4 8.4 7.8 7.98 Maximum U-235/
element, kgs 17.7 18.3 18.5 18.7 17.0(144"L) 16.6 19.0 Maximum U-235 19.8 (168"L) enrichment,w/o 4.0 3.65 4.0 3.65 3.65 4.0 3.85 (ii) Uranium dioxide as zircaloy clad unirrsdiated fuel elements contained within the Model No. RCC-4 packaging. Two (2) neutron ".bsorber plates consisting of 0.19" thick carbon steel are required between fuel elements of the following specifications.
17 x 17 Type ZR Clad Pellet diameter, in.
0.308 - 0.322 l
Rod diameter, in.
0.360 - 0.374 Maximum fuel length, in.
168
^
Maximum rods / element 264 Maximum cross section, (nom), in sq.
8.4 Maximum U-235/ element, kgs.
19.3 Maximum U-235 enrichment, w/o 3.55
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Page 3 - Certificate No. 5450 - Revision No.14 - Docket No. 71-5450 (iii) Uranium dioxide as zircaloy or stainless steel-clad unirradiated fuel rods of the following specifications:
Type SST Clad Zr Clad Zr Clad Pelletdiameter(nom),in 0.384 0.367 0.322 Roddiameter(nom),in 0.422 0.422 0.374' Fuel length (max), in 144 144 168 Maximum U-235 enrichment, w/o 4.0 4.0 3.65 (2) Maximum quantity of material per package (i)
For the contents described in 5(b)(1)(i) and 5(b)(1)(ii):
Two fuel elements.
(ii) For the contents described in 5(b)(1)(iii):
Two inner containers containing not more than 80 kilograms U-235.
5.
(c) Fissile Class II and III s
(1) flinimum transport index to be shown on label for Class II 1.2 (2) Maximum number of packages per shipment for Class III 60 6.
Fuel rods shall be closely packed in the fuel rod container on no more than an '
equivalent metal-to-metal square lattice.
Partially loaded fuel rod containers shall be fitted with a minimum of three, equally spaced blocks, of which the noncombustible portion of the blocks and the method by which they are secured shall assure that the rods are maintained on no more than an equivalent metal-to-metal square lattice within the fuel rod container.
7.
Each fuel assembly shall be unsheathed or shall be enclosed in an unsealed, poly-ethylene sheath which will not extend beyond the ends of the fuel assembly. The ends l
of the sheath shall not be folded or taped in any manner that would prevent the flow s
l of liquids into or out of the sheathed fuel assembly.
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o Page I - Certificate No. 5450 - Revision No.14
. Docket No. 71-5450 Alternatively, the fuel assenbly may be enclosed in an elongated plastic bag or
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sheath'along its full length.,At the bottom end of the fuel assembly, the bag will 1
be cut 'off or folded back to assure that the entire cross section of the lower end of the assembly is unobstructed. When folding is used, the portion of the sheath that is folded back will be cinched with tape near its end to hold it in place, and the length will.be such that when the assembly is loaded in the packaging, the folded sheath will be clamped in place in at least_two grid locations.
The top end of the bag may be gathered together and taped closed.
However, the top end then will be slit on all cFour sides. The slits will run perpendicular to the axis of the assembly
.and wi-11 extend the inner distance between the top nozzle pads and spring clamps (approximately 60% of the lpngth. of each side).
The slits will be made in a plane naar that formed by the top of the pads and clamps.
8.
The package authorized by this' certificate is hereby approved for use under the
. seneral license provisions of 10 CFR 571.12(b).
A 9.
Expiration'date: January,21,198'6.,
r REFERENCES
' 7 Westinghouse: Electric Corporatian application dated December 17, 1980.
Supplements [ dated: January 21 and September 4,1981.
[
t FOR THE U.S. NUCLEAR REGULATORY COMMISSION s,
k Charles E. MacDonald, Chief g
Transportation Certification Branch.
Division of Fuel Cycle and Material Safety 04tei 007 28 1981 s
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^f U.S. Nuclear Regulatory Commission 1
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b Transportation Certification Branch m
Approval Record Model No. RCC-4
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. Docket No. 71-5450
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By application dated Leptember 4,1981. Westinghouse Electric Corporation requested approval that-the RCC-4 container be modified to use carbon steel'for the neutron ubs'orber plates replacing (or.as alternates) the
'w
' copperTp]ates for use in Whipment of 17 x 17 LWR fuel assemblies with the following characteristics and. delimiting parameters:
l 17 x 17 ZR Clad Type i
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Pellet diac2ter, in.
0.308-0.322
. Rod diameter, in.
0.360-0.374 Maximum fuel length, in.
168 b_
Maximum rods / element 264
- Maximum cross section (nom), in sq.
8.4 s
Maximum U-235/elemer.t, kgs..
19.3
~ Maxinium U-235 enrichment, w/o
'3.55 The abov,e specified fuel assembly is to appear as 5(b)(1)(ii) page 2 of Certificate of Compliance No. 5450, Revision 14.
The contents (ii) of Revision 13 is 'to be redesignated as (iii).
The applicant performed a 3D-KEN 0 Ponte Carlo (19 neutron group cross section set) calculation for the e >bject fuel assembly in the RCC-4 container ender accident conditions with carbon steel as the absorbing ss clo:e,as possible $$(for 2 crushed containers (total of 4 assemblies plate. _The average k L
h absorber in place) was calculated to be 0.950 0.005.
i 1'This compares with previously calculated value of 0.941 0.005 for the same fuel 53ssembly having copper as the absorbing plate.
The staff has checked the detailed modelling of the submitted calculation and concurs that the geometry and materials are represented accurately
, for the ac.ident conuition postulated.
_ AdditionalJp, number densities, thickness, and fissionable mass limits-
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were verified using all the data supplied as input to the calculation.
[Since the methodology used by the applicant has previously successfully calculated a list set of critical benchmark experiments and for the
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'7 above notes reasons on the accurate KENO calculation, the staff recomends p'
approval in using the ca* bon steel absorbing plates in the RCC-4 for the
-17 x U fuel assembly.
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h Charles E. MacDonald, Chief t
Transportation Certification Branch i
h Division of Fuel Cycle and Material Safety, NMSS A m"
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