ML18064A265
| ML18064A265 | |
| Person / Time | |
|---|---|
| Site: | 07109248 |
| Issue date: | 03/01/2018 |
| From: | John Mckirgan Spent Fuel Licensing Branch |
| To: | Travis Tate Framatome |
| Devaser N | |
| Shared Package | |
| ML18064A263 | List: |
| References | |
| EPID L-2018-LLA-0027 | |
| Download: ML18064A265 (7) | |
Text
NRC FORM 618 (8-2000) 10 CFR 71
U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9248 25 71-9248 USA/9248/AF 1 OF 7 2. PREAMBLE a.This certificate is issued to certify that the package (packaging and contents) described in Item 5 below meets the applicable safety standards set forth in Title 10, Code of Federal Regulations, Part 71, "Packaging and Transportation of Radioactive Material." b.This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Departmen t 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 a. ISSUED TO (Name and Address) b.TITLE AND IDENTIFICATION OF REPORT OR APPLICATION Framatome Inc.
2101 Horn Rapids Road Richland, WA 99354 Framatome ANP, Inc. application dated September 5, 2003, as supplemented. 4.CONDITIONS This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and t he conditions specified below. 5. (a) Packaging (1) Model Nos.: SP-1, SP-2, and SP-3 (2) Description Fuel assembly and fuel rod shipping containers. The packages consist of a right rectangular metal inner container and a wooden outer container, with cushioning material between the inner and outer containers.
The metal inner container is approximately 11-1/2 inches by 18 inches by 179-1/2 inches long and is positioned within a wooden outer container approximately 30 inches by 31 inches by 207 inches long. The SP-1 and SP-2 packagings differ in the length of the metal inner container and end piece. The SP-3 packagings have a reduced spacing between the fuel assembly channels and the outer surface of the metal inner container. Cushioning is provided between the inner and outer containers by phenolic impregnated honeycomb and ethafoam, or equivalent. Closure of the metal inner container and the wooden outer container is accomplished by bolts. A pressure relief (breather) valve is provided on the inner container, and is set for 0.5 psi differential. The maximum weight of the packaging and contents is 2,800 pounds.
NRC FORM 618 (8-2000) 10 CFR 71
U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9248 25 71-9248 USA/9248/AF 2 OF 7 5.(a) (3) Drawings The packagings are fabricated and assembled in accordance with the following Framatome ANP, Inc., and Siemens Nuclear Power Corporation/Advanced Nuclear Fuels Corporation Drawing Nos.:
EMF-304,416, Rev. 14. EMF-306,272, Rev. 10.
EMF-309,141, Rev. 1.
5.(a) (4) Product Containers (i) Five-inch Schedule 40 stainless steel pipe fitted with screw type or flange closure. The product container shall be vented if it contains materials which decompose at less than
1475 ºF. (ii) Rod shipping container as shown on Siemens Power Corporation Drawing No. EMF-309,141, Rev. 1.
5.(b) Contents
(1) Type and form of material (i) UO 2 fuel assemblies in a 7 x 7, an 8 x 8, or a 9 x 9 square array with a maximum fuel cross-section area of 25 in 2, maximum fuel length of 174 inches, and maximum average enrichment of 3.3 wt.% U-235. Minimum Zircaloy clad thickness is 0.025 inches; maximum pellet diameter is 0.555 inches. Any number of water rods in any arrangement is permitted.
(ii) UO 2 fuel assemblies in a 7 x 7, an 8 x 8, or a 9 x 9 square array with a maximum fuel length of 174 inches, and a maximum average enrichment between 3.3 to 4.0 wt.% U-235. The maximum pellet diameter is 0.555 inch, and the minimum clad thickness is 0.025 inch. Any number of water rods in any arrangement is permitted, including part length rods. Each assembly contains at least 4 rods with nominal 2 wt.% Gd 2 O 3 , which are in non-perimeter locations and are symmetric about the diagonal.
(iii) UO 2 fuel assemblies with a maximum U-235 enrichment of 5.0 wt.%, and a maximum average U-235 planar enrichment of 4.0 wt.%. Each fuel assembly is made up of fuel rods in a 10 x 10 square array, with a maximum fuel cross section area of 25.221 in 2 , a nominal pitch of 0.511 inch, and a maximum fuel length of 174 inches. The maximum pellet diameter is 0.3356 inch, the minimum clad thickness is 0.0225 inch, and the maximum U-235 enrichment in any edge rod is 4.0 wt.%. Each assembly contains at least 6 rods with nominal 2 wt.% Gd 2 0 3, which are symmetric about the diagonal, and each assembly contains at least 4 water rods in the 4 central rod positions.
NRC FORM 618 (8-2000) 10 CFR 71
U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9248 25 71-9248 USA/9248/AF 3 OF 7 5.(b) (1) Type and form of material (Continued)
(iv) UO 2 fuel rods with a maximum U-235 enrichment of 5.0 wt.%, and a minimum Gd 2 O 3 content of 1.0 wt.%. The rods may be clad with Zircaloy, steel, or aluminum. The rods have a maximum fuel pellet diameter of 0.5 inch, and a maximum fuel length of 169 inches.
(v) UO 2 fuel assemblies composed of fuel rods in a 10 x 10 square array, with a maximum fuel cross section area of 25.0 in 2, and a maximum fuel length of 174 inches. The maximum U-235 enrichment is 5.0 wt.%, the maximum U-235 enrichment for all edge rods is 4.0 wt.%, and the maximum average planar enrichment, excluding perimeter rods and rods containing gadolinia (Gd 2 O 3), is 4.0 wt.% U-235. The maximum pellet diameter is 0.35 inch, and the minimum clad thickness is 0.018 inch. Each assembly must have a water channel in the central 3 x 3 rod positions. Any number of additional water rods in any arrangement is permitted, including part length rods. Each assembly must include at least twelve rods with a minimum nominal content of 2.0 wt.% gadolinia (Gd 2 O 3), in a pattern symmetric about one of the assembly diagonals. At least eight of the twelve gadolinia rods must be located in rows 2 and 9, and in columns 2 and 9 of the assembly.
(vi) UO 2 fuel assemblies composed of fuel rods in a 10 x 10 square array, with a maximum fuel cross section of 25.0 in 2, and a maximum fuel length of 174 inches. The maximum U-235 enrichment is 5.0 wt.%. The maximum pellet diameter is 0.35 inch, and the minimum clad thickness is 0.018 inch. Each assembly must have a water channel in the central 3 x 3 rod positions. Any number of additional water rods in any arrangement is permitted, including part length rods. Each assembly must include at least eight rods with a minimum nominal gadolinia (Gd 2 O 3) content of 2.0 wt.% in all axial regions with enriched pellets. Additional gadolinia rod specifications are included in supplement dated April 30, 1996.
(vii) UO 2 fuel assemblies composed of fuel rods in a 9 x 9 square array, with a maximum fuel cross section of 25.0 in 2, and a maximum fuel length of 174 inches. The maximum U-235 enrichment is 5.0 wt.%. The maximum pellet diameter is 0.40 inch, and the minimum clad thickness is 0.015 inch. Each assembly must have a water channel in the central 3 x 3 rod positions. Any number of additional water rods in any arrangement is permitted, including part length rods. Each assembly must include at least eight rods with a minimum nominal gadolinia (Gd 2 O 3) content of 2.0 wt.% in all axial regions with enriched pellets. Additional gadolinia rod specifications are included in supplement dated April 30, 1996.
NRC FORM 618 (8-2000) 10 CFR 71
U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9248 25 71-9248 USA/9248/AF 4 OF 7 5.(b) (1) Type and form of material (Continued)
(viii) UO 2 fuel assemblies composed of fuel rods in a 9 x 9 square array, with a maximum fuel cross-section area of 25.0 in 2, a maximum fuel length of 174 inches, and a maximum average uranium enrichment of 4.0 wt.% U-235. The nominal pellet diameter is 0.370 inch. At least the center 3 x 3 rod locations must be a water channel. Each assembly must include at least eight rods with a minimum nominal gadolinia (Gd 2 O 3) content of 2.0 wt. % in all axial regions with enriched pellets. The eight gadolinia rod locations are shown in Figure 1 of the supplement dated July 27, 1999.
(ix) UO 2 fuel assemblies composed of fuel rods in a 10 x 10 square array, with a maximum fuel cross section area of 25.0 in 2, and a maximum fuel length of 174 inches. The maximum U-235 enrichment is 5.0 wt.%, the maximum U-235 enrichment for all edge rods is 4.75 wt.%, the maximum U-235 enrichment for the four (4) corner edge rods is 3.05 wt. %, and the maximum U-235 enrichment for the eight (8) edge rods immediately adjacent to the four corner edge rods is 3.55 wt.%. The pellet diameter is between 0.30 and 0.3957 inch. Each assembly must have a water channel in a central 3 x 3 position. Any number of additional water rods in any arrangement is permitted, including part length rods. Each assembly must include at least 10 rods with a minimum nominal content of 2.0 wt.% gadolinia (Gd 2 O 3) in all axial regions with the enriched pellets, and in a pattern symmetric about one of the assembly diagonals. At least 10 gadolinia rods must be located in rows 2 and 9, and in columns 2 and 9 of the assembly and cannot be immediately adjacent to another one of the 10 gadolinia rods; however, diagonally adjacent is permitted. An additional upper tie plate (UTP) shipping shim may be added between the UTP and the fueled region. This UTP shim may consist of a maximum of
345 g plastic or plastic composite.
(x) UO 2 fuel assemblies composed of fuel rods in a 10 x 10 square array, with a maximum fuel cross section area of 25.0 in 2 and a maximum fuel length of 174 inches. The maximum uranium enrichment is 2.3 wt.% U-235. The pellet diameter is between 0.30 and 0.3957 inch. Each assembly must have a water channel in a central 3 x 3 position.
Any number of additional water rods in any arrangement is permitted, including part length rods. An additional upper tie plate (UTP) shipping shim may be added between the UTP and the fueled region. This UTP shim may consist of a maximum of 345 grams of plastic or plastic composite.
NRC FORM 618 (8-2000) 10 CFR 71
U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9248 25 71-9248 USA/9248/AF 5 OF 7 5.(b) (2) Maximum quantity of material per package Total weight of contents (fuel assemblies, or fuel rods and rod shipping containers) not to exceed 1265 pounds. Total quantity of radioactive material within a package may not exceed a Type A quantity.
(i) For the contents described in 5(b)(1)(i), 5(b)(1)(ii), 5(b)(1)(iii), 5(b)(1)(v), 5(b)(1)(vi), 5(b)(1)(vii), 5(b)(1)(viii), 5(b)(1)(ix), and 5(b)(1)(x):
Two full length fuel assemblies. Two short fuel assemblies may be substituted for each full length fuel assembly provided the two short assemblies are shipped end-to-end and the total fuel length does not exceed 174 inches.
(ii) For the contents described in 5(b)(1)(iv):
Two product containers specified in 5.(a)(4). Each product container may contain any number of loose fuel rods.
5.(c) Transport Index for Criticality Control (Criticality Safety Index)
Minimum transport index to be shown on label for nuclear criticality control:
(1) For contents described in 5(b)(1)(i),
5(b)(1)(ii), 5(b)(1)(iii), 5(b)(1)(iv), and 5(b)(1)(viii), and limited in 5(b)(2)(i) and 5(b)(2)(ii): 0.4 (2) For contents described in 5(b)(1)(v),
5(b)(1)(vi), 5(b)(1)(vii), 5(b)(1)(ix), 5(b)(1)(x),
and limited in 5(b)(2)(i): 1.0
- 6. Each fuel assembly must be unsheathed or must be enclosed in an unsealed, polyethylene sheath which may not extend beyond the ends of the fuel assembly. The ends of the sheath may not be folded or taped in any manner that would prevent the flow of liquids into or out of the sheathed fuel assembly.
- 7. Polyethylene shipping shims may be inserted between rods within fuel assemblies as follows:
(a) For contents described in 5(b)(1)(i) and 5(b)(1)(ii), up to a maximum of 0.20 gram H 2 O hydrogen equivalent per cubic centimeter averaged over the assembly.
NRC FORM 618 (8-2000) 10 CFR 71
U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9248 25 71-9248 USA/9248/AF 6 OF 7 7. Polyethylene shipping shims may be inserted between rods within fuel assemblies as follows (Cont.):
(b) For contents described in 5(b)(1)(v), up to a maximum of 0.25 gram H 2O hydrogen equivalent per cubic centimeter averaged over the assembly.
(c) For contents described in 5(b)(1)(viii), up to a maximum volume fraction of 0.13 averaged over the void volume of the assembly.
(d) For contents described in 5(b)(1)(iii), 5(b)(1)(vi), and 5(b)(1)(vii), polyethylene shipping shims are not permitted.
(e) For contents described in 5(b)(1)(ix) and 5(b)(1)(x), up to a maximum volume fraction of 0.14 averaged over the void volume of the assembly.
- 8. Only contents described in 5(b)(1)(viii) and 5(b)(1)(ix) are authorized for transport in Model No. SP-3 packages.
- 9. Maximum average enrichment means the highest average enrichment through any cross sectional plane of the assembly.
- 10. In addition to the requirements of Subpart G of 10 CFR Part 71:
(a) The package must be prepared for shipment and operated in accordance with the Operating Procedures in Chapter 7 of the application dated September 5, 2003, as supplemented.
(b) Each packaging must be acceptance tested and maintained in accordance with the Acceptance Tests and Maintenance Program in Chapter 8 of the application dated September 5, 2003, as supplemented.
- 11. The package authorized by this certificate is hereby authorized for use under the general license provisions of 10 CFR §71.17.
- 12. Transport by air of fissile material is not authorized.
- 13. Fabrication of new packagings is not authorized.
- 14. Revision 23 of this certificate may be used until December 31, 2017.
- 15. Expiration date: April 30, 2019.
NRC FORM 618 (8-2000) 10 CFR 71
U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9248 25 71-9248 USA/9248/AF 7 OF 7 REFERENCES Framatome ANP, Inc., application dated September 5, 2003.
Supplements dated: September 24, November 6, 2003, June 28, 2012, March 26, 2013, June 27, 2013, January 23 and 27, 2014, and November 18, 2016.
Framatome Inc., name change request dated January 17, 2018.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
/RA/
John McKirgan, Chief Spent Fuel Licensing Branch
Division of Spent Fuel Management
Office of Nuclear Material Safety
and Safeguards Date: 03/01/18