ML18064A076: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(Created page by program invented by StriderTol)
 
(12 intermediate revisions by the same user not shown)
Line 2: Line 2:
| number = ML18064A076
| number = ML18064A076
| issue date = 03/01/2018
| issue date = 03/01/2018
| title = Enclosure 1: Certificate of Compliance [Revision No. 9 of Certificate of Compliance No. 9319, for the Model Nos. MAP-12 and MAP-13 Transportation Packages]
| title = Enclosure 1: Certificate of Compliance (Revision No. 9 of Certificate of Compliance No. 9319, for the Model Nos. MAP-12 and MAP-13 Transportation Packages)
| author name = McKirgan J B
| author name = Mckirgan J
| author affiliation = NRC/NMSS/DSFM/SFLB
| author affiliation = NRC/NMSS/DSFM/SFLB
| addressee name = Tate T J
| addressee name = Tate T
| addressee affiliation = Framatome, Inc
| addressee affiliation = Framatome, Inc
| docket = 07109319
| docket = 07109319
| license number =  
| license number =  
| contact person = Devaser N J
| contact person = Devaser N
| case reference number = EPID L-2018-LLA-0026
| case reference number = EPID L-2018-LLA-0026
| package number = ML18064A073
| package number = ML18064A073
Line 15: Line 15:
| page count = 6
| page count = 6
| project = EPID:L-2018-LLA-0026
| project = EPID:L-2018-LLA-0026
| stage = Other
}}
}}


=Text=
=Text=
{{#Wiki_filter:NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES   9319 9 71-9319 USA/9319/B(U)F-96 1 OF 6   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. 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 a. ISSUED TO (Name and Address) b.TITLE AND IDENTIFICATION OF REPORT OR APPLICATION Framatome Inc. 2101 Horn Rapids Road Richland, WA 99354 TN Americas LLC, application dated November 8, 2017. 4.CONDITIONS This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below. 5. (a) Packaging (1) Model Nos.: MAP-12 and MAP-13 (2) Description The MAP package is designed to transport unirradiated uranium fuel assemblies with enrichment up to 5.0 weight percent. The package is designed to carry two fuel assemblies with core components. The package consists of two components: a base and lid. The containment system of the MAP package is the fuel rod cladding. The base consists of a fixed stainless steel strong-back which supports the fuel assemblies. A series of inner stiffeners are secured to the underside of the strong-back to support the fuel assemblies. A neutron moderator and absorber are positioned directly beneath the strong-back between each inner stiffener. The base inner stiffeners are retained by a stainless steel cover. Exterior to the cover is a layer of rigid polyurethane foam and an outer shell of 11 gauge stainless steel. A 12-gauge stainless steel sheet is provided between the two middle stiffeners.
{{#Wiki_filter:NRC FORM 618                                                                                                     U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
Four stainless steel outer stiffeners support the package base. The payload rests on the "W" shaped strong-back (referred to as a W-plate) and is held in place with hinged and latched aluminum doors. The lid is very similar to that of the base - a "W" shaped stainless steel inner shell is fitted with a series of inner stiffeners, neutron moderator and absorbers, and a stainless steel cover is fitted over the stiffeners. The lid is fitted with trapezoidal impact limiters at each end. The impact limiters are constructed from rigid polyurethane foam encased by the package outer stainless shell skin. The base and lid include end plates with interlocking, interfacing angles.  
: 1. a. CERTIFICATE NUMBER                           b. REVISION NUMBER     c. DOCKET NUMBER       d. PACKAGE IDENTIFICATION NUMBER       PAGE         PAGES 9319                                   9                   71-9319             USA/9319/B(U)F-96                     1 OF       6
: 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. 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
: a.       ISSUED TO (Name and Address)                                           b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION Framatome Inc.                                                             TN Americas LLC, application dated November 8, 2017.
2101 Horn Rapids Road Richland, WA 99354
: 4. CONDITIONS This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.
5.
(a)     Packaging (1)     Model Nos.:         MAP-12 and MAP-13 (2)     Description The MAP package is designed to transport unirradiated uranium fuel assemblies with enrichment up to 5.0 weight percent. The package is designed to carry two fuel assemblies with core components. The package consists of two components: a base and lid. The containment system of the MAP package is the fuel rod cladding.
The base consists of a fixed stainless steel strong-back which supports the fuel assemblies. A series of inner stiffeners are secured to the underside of the strong-back to support the fuel assemblies. A neutron moderator and absorber are positioned directly beneath the strong-back between each inner stiffener. The base inner stiffeners are retained by a stainless steel cover.
Exterior to the cover is a layer of rigid polyurethane foam and an outer shell of 11 gauge stainless steel. A 12-gauge stainless steel sheet is provided between the two middle stiffeners.
Four stainless steel outer stiffeners support the package base. The payload rests on the W shaped strong-back (referred to as a W-plate) and is held in place with hinged and latched aluminum doors. The lid is very similar to that of the base - a W shaped stainless steel inner shell is fitted with a series of inner stiffeners, neutron moderator and absorbers, and a stainless steel cover is fitted over the stiffeners. The lid is fitted with trapezoidal impact limiters at each end. The impact limiters are constructed from rigid polyurethane foam encased by the package outer stainless shell skin. The base and lid include end plates with interlocking, interfacing angles.


NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES   9319 9 71-9319 USA/9319/B(U)F-96 2 OF 6   5.(a) (2) Description (continued)
NRC FORM 618                                                                                 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
: 1. a. CERTIFICATE NUMBER                 b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE     PAGES 9319                           9             71-9319       USA/9319/B(U)F-96               2 OF     6 5.(a)         (2)   Description (continued)
There are two models of the MAP package, the MAP-12 and MAP-13. The weights and dimensions of the package are as follows:
There are two models of the MAP package, the MAP-12 and MAP-13. The weights and dimensions of the package are as follows:
MAP-12 (for 144-in Maximum Nominal Active Fuel Length): Maximum Gross Weight 8,630 lbs Maximum Payload Weight 3,400 lbs Outer Dimensions Length   208 in Width   45 in Height    31 in  
MAP-12 (for 144-in Maximum Nominal Active Fuel Length):
Maximum Gross Weight                       8,630 lbs Maximum Payload Weight                     3,400 lbs Outer Dimensions Length                             208 in Width                             45 in Height                            31 in MAP-13 (for 150-in Maximum Nominal Active Fuel Length):
Maximum Gross Weight                      8,630 lbs Maximum Payload Weight                    3,400 lbs Outer Dimensions Length                            221 in Width                              45 in Height                             31 in (3)    Drawings The MAP-12 and MAP-13 packages are fabricated and assembled in accordance with the following AREVA NP, Inc. Drawing Nos.:
9045393, Rev. 6;                          9045402, Rev. 4; 9045397, Rev. 1;                          9045403, Rev. 3; 9045399, Rev. 2;                          9045404, Rev. 3; 9045401, Rev. 3;                          9045405, Rev. 3.
(b)    Contents (1)   Type and Form of Material Enriched commercial grade uranium or enriched reprocessed uranium, as defined in ASTM C996-04, oxide fuel rods enriched to no more than 5.0 weight percent in the U-235 isotope, with limits specified in Table 1 below.


MAP-13 (for 150-in Maximum Nominal Active Fuel Length): Maximum Gross Weight  8,630 lbs Maximum Payload Weight  3,400 lbs Outer Dimensions  Length    221 in Width    45 in Height    31 in (3) Drawings  The MAP-12 and MAP-13 packages are fabricated and assembled in accordance with the following AREVA NP, Inc. Drawing Nos.:
NRC FORM 618                                                                                   U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
9045393, Rev. 6;    9045402, Rev. 4; 9045397, Rev. 1;    9045403, Rev. 3; 9045399, Rev. 2;    9045404, Rev. 3; 9045401, Rev. 3;    9045405, Rev. 3.  (b) Contents  (1) Type and Form of Material Enriched commercial grade uranium or enriched reprocessed uranium, as defined in ASTM C996-04, oxide fuel rods enriched to no more than 5.0 weight percent in the U-235 isotope, with limits specified in Table 1 below.
: 1. a. CERTIFICATE NUMBER           b. REVISION NUMBER   c. DOCKET NUMBER     d. PACKAGE IDENTIFICATION NUMBER PAGE     PAGES 9319                     9                 71-9319           USA/9319/B(U)F-96               3 OF     6 5.(b)         Contents (continued)
NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES   9319 9 71-9319 USA/9319/B(U)F-96 3 OF 6   5.(b) Contents (continued)
(2)   Maximum Quantity of Material per Package Table 1: Maximum Authorized Concentrations Isotope               Maximum Content U-232                  2.00 x 10-9 g/g U U-234                 2.00 x 10-3 g/g U U-235                 5.00 x 10-2 g/g U U-236                  2.50 x 10-2 g/g U U-238                 Balance of Uranium Np-237                 1.66 x 10-6 g/g U Pu-238                6.20 x 10-11 g/g U Pu-239                 3.04 x 10-9 g/g U Pu-240                 3.04 x 10-9 g/g U Gamma Emitters          5.18 x 105 MeV - Bq/kg U
  (2) Maximum Quantity of Material per Package Table 1: Maximum Authorized Concentrations Isotope Maximum Content U-2322.00 x 10-9 g/g UU-234 2.00 x 10-3 g/g U U-235 5.00 x 10-2 g/g U U-2362.50 x 10-2 g/g UU-238 Balance of Uranium Np-237 1.66 x 10-6 g/g U Pu-2386.20 x 10-11 g/g UPu-239 3.04 x 10-9 g/g U Pu-240 3.04 x 10-9 g/g U Gamma Emitters5.18 x 105 MeV - Bq/kg U NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES  1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE  PAGES    9319 9 71-9319 USA/9319/B(U)F-96 4 OF 6  5.(b) Contents (continued) 
(3) Fuel Assembly (i) The parameters of the fuel assemblies that are permitted are specified in the table below. Fuel Rod Array 14x14 15x15 16x16 17x17 Assembly Type 1 2 1 2 3 1 1 2 No. of Fuel Rods 176 179 208 216 204 236 264 264 No. of Non-Fuel Cells 20 17 17 9 21 20 25 25 Nominal Fuel Rod Pitch (in) 0.580 0.556 0.568 0.550 0.563 0.506 0.502 0.496 Maximum Pellet Outer Diameter (in) 0.3812 0.3682 0.3622 0.3707 0.3742 0.3617 0.3682 0.3282 0.3252 0.3232Minimum Fuel Rod Outer Diameter (in) 0.438 0.422 0.414 0.428 0.428 0.414 0.422 0.380 0.377 0.372 Minimum Clad Wall Thickness (in) 0.0245 0.0230 0.0220 0.0245 0.0230 0.0220 0.0230 0.0220 0.0220 0.0205Minimum Guide Tube Wall Thickness (in) N/A N/A 0.0140 N/A N/A N/A N/A N/A N/A  N/A Minimum Guide Tube Outer Diameter (in) N/A N/A 0.528 N/A N/A N/A N/A N/A N/A N/A Number of Guide Tubes N/A N/A 16 N/A N/A N/A N/A N/A N/A N/A Minimum Instrument Tube Wall Thickness (in) N/A N/A 0.0240N/A N/A N/A N/A N/A N/A  N/A Minimum Instrument Tube Outer Diameter (in) N/A N/A 0.491 N/A N/A N/A N/A N/A N/A N/A Number of Instrument Tubes N/A N/A 1 N/A N/A N/A N/A N/A N/A N/A Clad/Tube Material Type Zr Alloy Zr Alloy Zr Alloy Zr Alloy Zr Alloy Zr Alloy Zr Alloy Zr Alloy Maximum Active Fuel Length (in) 160 160 160 160 160 160 160 160 NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES  1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE  PAGES    9319 9 71-9319 USA/9319/B(U)F-96 5 OF 6  5.(b) Contents (continued)  (3) Fuel Assembly (continued)
(ii) Non-fissile base-plate mounted and spider body core components are permitted.  (iii) Fuel rods assembled into the fuel assemblies are those loaded with sintered pellets of uranium oxides and/or with sintered pellets of uranium oxides mixed with various additives (e.g., Chromium, Boron, Gadolinium, and Europium).  (c) Criticality Safety Index: 2.8 6. In addition to the requirements of Subpart G of 10 CFR Part 71:


   (a) The package shall be prepared for shipment and operated in accordance with the Package Operations in Section 7 of the application, as supplemented.    (b) Each package must meet the Acceptance Tests and Maintenance Program of Section 8 of the application, as supplemented.   
NRC FORM 618                                                                                    U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
   (c) Each fuel assembly must be unsheathed or must be enclosed in an unsealed, polyethylene or polypropylene 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.   (d) The fuel rods must be leak tested after fabrication to ensure that the leakage rate of the containment boundary is less than 1E-7 ref cc/sec. 7. Transport by air of fissile material is not authorized.
: 1. a. CERTIFICATE NUMBER              b. REVISION NUMBER    c. DOCKET NUMBER    d. PACKAGE IDENTIFICATION NUMBER   PAGE          PAGES 9319                        9                71-9319          USA/9319/B(U)F-96                  4    OF      6 5.(b)        Contents (continued)
(3)    Fuel Assembly (i)   The parameters of the fuel assemblies that are permitted are specified in the table below.
Fuel Rod Array              14x14                                15x15                            16x16        17x17 Assembly Type                  1        2                    1                    2          3          1      1        2 No. of Fuel Rods              176        179                  208                216        204        236    264      264 No. of Non-Fuel Cells          20        17                    17                    9          21          20      25      25 Nominal Fuel Rod Pitch      0.580      0.556                0.568              0.550      0.563      0.506  0.502   0.496 (in)
Maximum Pellet Outer        0.3812    0.3682      0.3622    0.3707    0.3742  0.3617      0.3682      0.3282 0.3252  0.3232 Diameter (in)
Minimum Fuel Rod            0.438      0.422      0.414      0.428      0.428    0.414      0.422      0.380   0.377    0.372 Outer Diameter (in)
Minimum Clad Wall            0.0245    0.0230      0.0220    0.0245    0.0230  0.0220      0.0230      0.0220  0.0220  0.0205 Thickness (in)
Minimum Guide Tube            N/A        N/A      0.0140      N/A        N/A      N/A        N/A        N/A    N/A Wall Thickness (in)                                                                                                        N/A Minimum Guide Tube            N/A        N/A      0.528      N/A        N/A      N/A        N/A        N/A    N/A      N/A Outer Diameter (in)
Number of Guide              N/A        N/A        16        N/A        N/A      N/A        N/A        N/A    N/A      N/A Tubes Minimum Instrument Tube Wall Thickness          N/A        N/A      0.0240      N/A        N/A      N/A        N/A        N/A    N/A N/A (in)
Minimum Instrument Tube Outer Diameter          N/A        N/A      0.491      N/A        N/A      N/A        N/A        N/A    N/A      N/A (in)
Number of Instrument          N/A        N/A          1        N/A        N/A      N/A        N/A        N/A    N/A      N/A Tubes Clad/Tube Material            Zr        Zr                    Zr                  Zr          Zr          Zr      Zr      Zr Type                          Alloy    Alloy                Alloy                Alloy      Alloy        Alloy  Alloy    Alloy Maximum Active Fuel          160        160                  160                160        160        160    160      160 Length (in)


8. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17. 9. Expiration date: February 28, 2023.  
NRC FORM 618                                                                                U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
: 1. a. CERTIFICATE NUMBER                b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE      PAGES 9319                          9              71-9319      USA/9319/B(U)F-96              5  OF    6 5.(b)        Contents (continued)
(3)    Fuel Assembly (continued)
(ii)    Non-fissile base-plate mounted and spider body core components are permitted.
(iii)  Fuel rods assembled into the fuel assemblies are those loaded with sintered pellets of uranium oxides and/or with sintered pellets of uranium oxides mixed with various additives (e.g., Chromium, Boron, Gadolinium, and Europium).
(c)    Criticality Safety Index:          2.8
: 6.        In addition to the requirements of Subpart G of 10 CFR Part 71:
(a)      The package shall be prepared for shipment and operated in accordance with the Package Operations in Section 7 of the application, as supplemented.
(b)      Each package must meet the Acceptance Tests and Maintenance Program of Section 8 of the application, as supplemented.
(c)      Each fuel assembly must be unsheathed or must be enclosed in an unsealed, polyethylene or polypropylene 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.
(d)      The fuel rods must be leak tested after fabrication to ensure that the leakage rate of the containment boundary is less than 1E-7 ref cc/sec.
: 7.        Transport by air of fissile material is not authorized.
: 8.        The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.
: 9.         Expiration date: February 28, 2023.


NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES   9319 9 71-9319 USA/9319/B(U)F-96 6 OF 6   REFERENCES TN Americas LLC, application dated November 8, 2017.  
NRC FORM 618                                                                         U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
 
: 1. a. CERTIFICATE NUMBER       b. REVISION NUMBER   c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE     PAGES 9319                 9                 71-9319       USA/9319/B(U)F-96               6 OF     6 REFERENCES TN Americas LLC, application dated November 8, 2017.
Framatome Inc., name change request dated January 17, 2018.    
Framatome Inc., name change request dated January 17, 2018.
 
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
                                                      /RA/
            /RA/ John McKirgan, Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards Date: 03/01/18
John McKirgan, Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards Date: 03/01/18}}
}}

Latest revision as of 17:30, 21 October 2019

Enclosure 1: Certificate of Compliance (Revision No. 9 of Certificate of Compliance No. 9319, for the Model Nos. MAP-12 and MAP-13 Transportation Packages)
ML18064A076
Person / Time
Site: 07109319
Issue date: 03/01/2018
From: John Mckirgan
Spent Fuel Licensing Branch
To: Travis Tate
Framatome
Devaser N
Shared Package
ML18064A073 List:
References
EPID L-2018-LLA-0026
Download: ML18064A076 (6)
v • d • e


Text

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9319 9 71-9319 USA/9319/B(U)F-96 1 OF 6
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. 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
a. ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION Framatome Inc. TN Americas LLC, application dated November 8, 2017.

2101 Horn Rapids Road Richland, WA 99354

4. CONDITIONS This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

5.

(a) Packaging (1) Model Nos.: MAP-12 and MAP-13 (2) Description The MAP package is designed to transport unirradiated uranium fuel assemblies with enrichment up to 5.0 weight percent. The package is designed to carry two fuel assemblies with core components. The package consists of two components: a base and lid. The containment system of the MAP package is the fuel rod cladding.

The base consists of a fixed stainless steel strong-back which supports the fuel assemblies. A series of inner stiffeners are secured to the underside of the strong-back to support the fuel assemblies. A neutron moderator and absorber are positioned directly beneath the strong-back between each inner stiffener. The base inner stiffeners are retained by a stainless steel cover.

Exterior to the cover is a layer of rigid polyurethane foam and an outer shell of 11 gauge stainless steel. A 12-gauge stainless steel sheet is provided between the two middle stiffeners.

Four stainless steel outer stiffeners support the package base. The payload rests on the W shaped strong-back (referred to as a W-plate) and is held in place with hinged and latched aluminum doors. The lid is very similar to that of the base - a W shaped stainless steel inner shell is fitted with a series of inner stiffeners, neutron moderator and absorbers, and a stainless steel cover is fitted over the stiffeners. The lid is fitted with trapezoidal impact limiters at each end. The impact limiters are constructed from rigid polyurethane foam encased by the package outer stainless shell skin. The base and lid include end plates with interlocking, interfacing angles.

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9319 9 71-9319 USA/9319/B(U)F-96 2 OF 6 5.(a) (2) Description (continued)

There are two models of the MAP package, the MAP-12 and MAP-13. The weights and dimensions of the package are as follows:

MAP-12 (for 144-in Maximum Nominal Active Fuel Length):

Maximum Gross Weight 8,630 lbs Maximum Payload Weight 3,400 lbs Outer Dimensions Length 208 in Width 45 in Height 31 in MAP-13 (for 150-in Maximum Nominal Active Fuel Length):

Maximum Gross Weight 8,630 lbs Maximum Payload Weight 3,400 lbs Outer Dimensions Length 221 in Width 45 in Height 31 in (3) Drawings The MAP-12 and MAP-13 packages are fabricated and assembled in accordance with the following AREVA NP, Inc. Drawing Nos.:

9045393, Rev. 6; 9045402, Rev. 4; 9045397, Rev. 1; 9045403, Rev. 3; 9045399, Rev. 2; 9045404, Rev. 3; 9045401, Rev. 3; 9045405, Rev. 3.

(b) Contents (1) Type and Form of Material Enriched commercial grade uranium or enriched reprocessed uranium, as defined in ASTM C996-04, oxide fuel rods enriched to no more than 5.0 weight percent in the U-235 isotope, with limits specified in Table 1 below.

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9319 9 71-9319 USA/9319/B(U)F-96 3 OF 6 5.(b) Contents (continued)

(2) Maximum Quantity of Material per Package Table 1: Maximum Authorized Concentrations Isotope Maximum Content U-232 2.00 x 10-9 g/g U U-234 2.00 x 10-3 g/g U U-235 5.00 x 10-2 g/g U U-236 2.50 x 10-2 g/g U U-238 Balance of Uranium Np-237 1.66 x 10-6 g/g U Pu-238 6.20 x 10-11 g/g U Pu-239 3.04 x 10-9 g/g U Pu-240 3.04 x 10-9 g/g U Gamma Emitters 5.18 x 105 MeV - Bq/kg U

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9319 9 71-9319 USA/9319/B(U)F-96 4 OF 6 5.(b) Contents (continued)

(3) Fuel Assembly (i) The parameters of the fuel assemblies that are permitted are specified in the table below.

Fuel Rod Array 14x14 15x15 16x16 17x17 Assembly Type 1 2 1 2 3 1 1 2 No. of Fuel Rods 176 179 208 216 204 236 264 264 No. of Non-Fuel Cells 20 17 17 9 21 20 25 25 Nominal Fuel Rod Pitch 0.580 0.556 0.568 0.550 0.563 0.506 0.502 0.496 (in)

Maximum Pellet Outer 0.3812 0.3682 0.3622 0.3707 0.3742 0.3617 0.3682 0.3282 0.3252 0.3232 Diameter (in)

Minimum Fuel Rod 0.438 0.422 0.414 0.428 0.428 0.414 0.422 0.380 0.377 0.372 Outer Diameter (in)

Minimum Clad Wall 0.0245 0.0230 0.0220 0.0245 0.0230 0.0220 0.0230 0.0220 0.0220 0.0205 Thickness (in)

Minimum Guide Tube N/A N/A 0.0140 N/A N/A N/A N/A N/A N/A Wall Thickness (in) N/A Minimum Guide Tube N/A N/A 0.528 N/A N/A N/A N/A N/A N/A N/A Outer Diameter (in)

Number of Guide N/A N/A 16 N/A N/A N/A N/A N/A N/A N/A Tubes Minimum Instrument Tube Wall Thickness N/A N/A 0.0240 N/A N/A N/A N/A N/A N/A N/A (in)

Minimum Instrument Tube Outer Diameter N/A N/A 0.491 N/A N/A N/A N/A N/A N/A N/A (in)

Number of Instrument N/A N/A 1 N/A N/A N/A N/A N/A N/A N/A Tubes Clad/Tube Material Zr Zr Zr Zr Zr Zr Zr Zr Type Alloy Alloy Alloy Alloy Alloy Alloy Alloy Alloy Maximum Active Fuel 160 160 160 160 160 160 160 160 Length (in)

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9319 9 71-9319 USA/9319/B(U)F-96 5 OF 6 5.(b) Contents (continued)

(3) Fuel Assembly (continued)

(ii) Non-fissile base-plate mounted and spider body core components are permitted.

(iii) Fuel rods assembled into the fuel assemblies are those loaded with sintered pellets of uranium oxides and/or with sintered pellets of uranium oxides mixed with various additives (e.g., Chromium, Boron, Gadolinium, and Europium).

(c) Criticality Safety Index: 2.8

6. In addition to the requirements of Subpart G of 10 CFR Part 71:

(a) The package shall be prepared for shipment and operated in accordance with the Package Operations in Section 7 of the application, as supplemented.

(b) Each package must meet the Acceptance Tests and Maintenance Program of Section 8 of the application, as supplemented.

(c) Each fuel assembly must be unsheathed or must be enclosed in an unsealed, polyethylene or polypropylene 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.

(d) The fuel rods must be leak tested after fabrication to ensure that the leakage rate of the containment boundary is less than 1E-7 ref cc/sec.

7. Transport by air of fissile material is not authorized.
8. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.
9. Expiration date: February 28, 2023.

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9319 9 71-9319 USA/9319/B(U)F-96 6 OF 6 REFERENCES TN Americas LLC, application dated November 8, 2017.

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

Retrieved from "https://kanterella.com/w/index.php?title=ML18064A076&oldid=1946451"