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| number = ML18026A875
| number = ML18026A875
| issue date = 01/26/2018
| issue date = 01/26/2018
| title = Enclosure 1: Certificate of Compliance No. 9355, Revision No. 2 [Letter to A. M. Al-Daouk Revision No. 2 of Certificate of Compliance No. 9355 for the Model No. 435-B Transportation Package]
| title = Enclosure 1: Certificate of Compliance No. 9355, Revision No. 2 (Letter to A. M. Al-Daouk Revision No. 2 of Certificate of Compliance No. 9355 for the Model No. 435-B Transportation Package)
| author name = Rahimi M
| author name = Rahimi M
| author affiliation = NRC/NMSS/DSFM/SFLB
| author affiliation = NRC/NMSS/DSFM/SFLB
| addressee name = Al-Daouk A M
| addressee name = Al-Daouk A
| addressee affiliation = US Dept of Energy (DOE)
| addressee affiliation = US Dept of Energy (DOE)
| docket = 07109355
| docket = 07109355
| license number =  
| license number =  
| contact person = Allen W C
| contact person = Allen W
| case reference number = EPID L-2017-LLA-0053
| case reference number = EPID L-2017-LLA-0053
| package number = ML18026A874
| package number = ML18026A874
Line 15: Line 15:
| page count = 6
| page count = 6
| project = EPID:L-2017-LLA-0053
| project = EPID:L-2017-LLA-0053
| 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   9355 2 71-9355 USA/9355/B(U)-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   National Nuclear Security Administration P.O. Box 5400 Albuquerque,  NM 87185 National Nuclear Security Administration application dated April 27, 2017, as supplemented. 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 No.: 435-B (2) Description The Model No. 435-B package consists of multiple configurations. The package is a Category I container. When loaded and prepared for transport, the external dimensions of the 435-B package are approximately 83 inches (in.) (210.8 centimeters (cm)) tall and 70 in. (177.8 cm) in diameter (over the lower impact limiter). The maximum weight of the package is 10,100 pounds (lbs) (4,545.5 kilograms (kg)).  
{{#Wiki_filter: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 9355                               2                   71-9355             USA/9355/B(U)-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 National Nuclear Security Administration                               National Nuclear Security Administration application P.O. Box 5400                                                           dated April 27, 2017, as supplemented.
Albuquerque, NM 87185
: 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 No.:           435-B (2)       Description The Model No. 435-B package consists of multiple configurations. The package is a Category I container. When loaded and prepared for transport, the external dimensions of the 435-B package are approximately 83 inches (in.) (210.8 centimeters (cm)) tall and 70 in. (177.8 cm) in diameter (over the lower impact limiter). The maximum weight of the package is 10,100 pounds (lbs) (4,545.5 kilograms (kg)).
Unless noted in the application, all elements of the 435-B package are made of Type 304 stainless steel in conformance with the American Standards for Testing Materials (ASTM) A240. The major components of the package include:
(i)        A baseThe base consists of the lower torispherical head, lower flange, lower internal impact limiter, and external impact limiter. The volume inside the external impact limiter is filled with 15 pounds per cubic feet (lb/ft3) polyurethane foam poured in place. The inside surface of the bottom shell is covered with a 1/4-inch thick layer of refractory insulation paper. A full penetration weld connects the lower torispherical head (1/2-inch thick plate) to the lower flange.
(ii)      A bellThe bell consists of the upper torispherical head, cylindrical shell, upper flange, vent and test port blocks, upper internal impact limiter, dual side thermal shield, head thermal shield, and the closure bolt access tube structure. Two, 1/4-inch thick, layers of refractory insulation paper cover the area of the containment wall adjacent to the tubes. Machined blocks of 30 lb/ft3 polyurethane foam are located between the tubes.


Unless noted in the application, all elements of the 435-B package are made of Type 304 stainless steel in conformance with the American Standards for Testing Materials (ASTM) A240. The major components of the package include: 
NRC FORM 618                                                                             U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
(i) A base-The base consists of the lower torispherical head, lower flange, lower internal impact limiter, and external impact limiter. The volume inside the external impact limiter is filled with 15 pounds per cubic feet (lb/ft3) polyurethane foam poured in place. The inside surface of the bottom shell is covered with a 1/4-inch thick layer of refractory insulation paper. A full penetration weld connects the lower torispherical head (1/2-inch thick plate) to the lower flange.  (ii) A bell-The bell consists of the upper torispherical head, cylindrical shell, upper flange, vent and test port blocks, upper internal impact limiter, dual side thermal shield, head thermal shield, and the closure bolt access tube structure. Two, 1/4-inch thick, layers of refractory insulation paper cover the area of the containment wall adjacent to the tubes. Machined blocks of 30 lb/ft3 polyurethane foam are located between the tubes.
: 1. a. CERTIFICATE NUMBER               b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE     PAGES 9355                         2             71-9355       USA/9355/B(U)-96                 2 OF   6 5.(a)     Packaging (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   9355 2 71-9355 USA/9355/B(U)-96 2 OF 6   5.(a) Packaging (Continued) (2) Description (iii) An internal lodgment, made of aluminum, which supports the Long Term Storage Shield (LTSS)-The lodgment and the inner container designs allow maintaining the position of the payload in the package cavity during normal conditions of transport and hypothetical accident conditions. The LTSS rests on a 1/2-inch thick plate covered with a 1/2-inch thick layer of neoprene rubber. (iv) LTSS-The LTSS consists of a central steel magazine, or barrel, surrounded by thick lead encased in a steel shell. The barrel contains four longitudinal holes, each of which can accommodate one drawer assembly. (v) An inner container, which supports shielded devices-The inner container holds a shielded device and provides support for the device and the blocking (dunnage) materials during transport. (vi) Two internal impact limiters-The internal impact limiters located at each end of the payload cavity include an array of 130 ASTM A249 or A269, Type TP304, stainless steel tubes. The impact limiters are curved on one side to match the inside of the torispherical head, and flat on the other. Each of the 130 tubes is tack-welded in three places to a stainless steel tube stabilizer sheet. Four stainless steel clips welded to the inner surface of the containment boundary in the lower and upper position hold the internal impact limiters in place. The LTSS or shielded devices provide shielding. Shielding materials are lead, tungsten, steel, or depleted uranium. The LTSS provides the shielding for the sealed capsule content specified in Tables 1 and 2. Therefore, these sources must be packed in the LTSS drawer(s). The shielded devices, identified in Table 3, are self-shielding, and must be packed in an inner container for shipment as specified in Table 4.  
(2)       Description (iii)   An internal lodgment, made of aluminum, which supports the Long Term Storage Shield (LTSS)The lodgment and the inner container designs allow maintaining the position of the payload in the package cavity during normal conditions of transport and hypothetical accident conditions. The LTSS rests on a 1/2-inch thick plate covered with a 1/2-inch thick layer of neoprene rubber.
(3) Drawings The packaging is constructed in accordance with AREVA Federal Services LLC drawings:
(iv)     LTSSThe LTSS consists of a central steel magazine, or barrel, surrounded by thick lead encased in a steel shell. The barrel contains four longitudinal holes, each of which can accommodate one drawer assembly.
: 1) 1916-01-01-SAR, "435-B Package Assembly SAR Drawing," sheets 1-7, Revision 6 2) 1916-01-02-SAR, "435-B LTSS Lodgment SAR Drawing," sheets 1-2, Revision 4 3) 1916-01-03-SAR, "435-B Inner Container SAR Drawing," sheets 1-2, Revision 4 5.(b) Contents (1) Type and form of material Radioactive sealed sources of isotopes described in Tables 1 and 2.  
(v)     An inner container, which supports shielded devicesThe inner container holds a shielded device and provides support for the device and the blocking (dunnage) materials during transport.
(vi)     Two internal impact limitersThe internal impact limiters located at each end of the payload cavity include an array of 130 ASTM A249 or A269, Type TP304, stainless steel tubes. The impact limiters are curved on one side to match the inside of the torispherical head, and flat on the other. Each of the 130 tubes is tack-welded in three places to a stainless steel tube stabilizer sheet. Four stainless steel clips welded to the inner surface of the containment boundary in the lower and upper position hold the internal impact limiters in place.
The LTSS or shielded devices provide shielding. Shielding materials are lead, tungsten, steel, or depleted uranium. The LTSS provides the shielding for the sealed capsule content specified in Tables 1 and 2. Therefore, these sources must be packed in the LTSS drawer(s). The shielded devices, identified in Table 3, are self-shielding, and must be packed in an inner container for shipment as specified in Table 4.
(3)       Drawings The packaging is constructed in accordance with AREVA Federal Services LLC drawings:
: 1) 1916-01-01-SAR, 435-B Package Assembly SAR Drawing, sheets 1-7, Revision 6
: 2) 1916-01-02-SAR, 435-B LTSS Lodgment SAR Drawing, sheets 1-2, Revision 4
: 3) 1916-01-03-SAR, 435-B Inner Container SAR Drawing, sheets 1-2, Revision 4 5.(b)     Contents (1)       Type and form of material Radioactive sealed sources of isotopes described in Tables 1 and 2.


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   9355 2 71-9355 USA/9355/B(U)-96 3 OF 6   5.(b) Contents (Continued)   (2) Maximum quantity of material per package (i) LTSS   Table 1. Maximum Activity of LTSS Payload Source Nuclides 1, 2 Nuclide Maximum Activity Ci 60Co 12,970 137Cs 14,000 90Sr 1,000 --- --- --- --- 241Am (no Be) 3 1,000 241Am Be 3 6.6 192Ir 200 75Se 80 Notes: 1. Physical form of all nuclides is solid material in a sealed capsule. 2. The maximum activity listed is the maximum for a single nuclide in the LTSS. For combinations of different nuclides, lower activity limits apply as discussed in Chapter 5, "Shielding Evaluation," and Operating Procedures in Chapter 7 of the application.
NRC FORM 618                                                                                   U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
3. Impurities may include oxygen and chlorine. Table 2. Maximum Mass of LTSS Payload Source Nuclides. 1, 2 Nuclide Maximum Mass grams of Pu 238Pu (no Be) 75 g Pu 239Pu (no Be) 15 g Pu 239Pu Be 15 g Pu Notes: 1. Physical form of all nuclides is solid material in a sealed capsule.  
: 1. a. CERTIFICATE NUMBER             b. REVISION NUMBER     c. DOCKET NUMBER   d. PACKAGE IDENTIFICATION NUMBER PAGE     PAGES 9355                       2                   71-9355         USA/9355/B(U)-96                 3 OF   6 5.(b)     Contents (Continued)
(2)       Maximum quantity of material per package (i)     LTSS Table 1. Maximum Activity of LTSS Payload Source Nuclides 1, 2 Maximum Activity Nuclide Ci 60Co                                   12,970 137Cs                                 14,000 90Sr                                   1,000 241Am (no Be) 3                               1,000 241Am Be 3                                   6.6 192Ir                                   200 75Se                                     80 Notes:
: 1. Physical form of all nuclides is solid material in a sealed capsule.
: 2. The maximum activity listed is the maximum for a single nuclide in the LTSS. For combinations of different nuclides, lower activity limits apply as discussed in Chapter 5, Shielding Evaluation, and Operating Procedures in Chapter 7 of the application.
: 3. Impurities may include oxygen and chlorine.
Table 2. Maximum Mass of LTSS Payload Source Nuclides. 1, 2 Maximum Mass Nuclide grams of Pu 238Pu (no Be)                     75 g Pu 239Pu (no Be)                     15 g Pu 239Pu Be                       15 g Pu Notes:
: 1. Physical form of all nuclides is solid material in a sealed capsule.
: 2. Impurities may include oxygen.
: 2. Impurities may include oxygen.
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    9355 2 71-9355 USA/9355/B(U)-96 4 OF 6  5.(b) Contents (Continued)  (2) Maximum quantity of material per package (Continued) 
  (ii) Inner Container-Shielded Devices Table 3. Maximum Activity and Weight of Shielded Devices 1  Model Name/Type Maximum Activity Ci Nominal Weight 2 lbs. Sealed Source Device Registry No.2 Group 1 Devices Gammator 50B, B, B34, G-50-B 420 1,800 NR-0880-D-802-S Gammator M34 1,920 1,850 NR-0880-D-806-S Gammator M38 3,840 2,250 NR-0880-D-806-S Gammacell 1000 (GC-1000)  -Models A through D 
-Elite A through D, Type I and Type II 3,840 (bounding value) 2,800 NR-0880-D-808-S, NR-1307-D-102-S Gammacell 3000 (GC-3000) 
-Elan A through C, Type I and Type II 3,048 3,300 NR-1307-D-102-S Group 3 Devices Gammacell-40 (GC-40 Exactor)  2,250 3 2,650 NR-1307-D-101-S  Notes: 1. Radionuclide in all cases is 137Cs. 2. Consult NRC's Sealed Source Device Registry for design and safety features of each model. 3. GC-40 activity is given for one of the two device components that make up a complete  GC-40. Only one device component may be shipped at one time.    (3) Maximum weight of contents  (i) LTSS  For the LTSS, the payload of isotopes other than plutonium is limited by the activity rather than their weight.
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    9355 2 71-9355 USA/9355/B(U)-96 5 OF 6  5.(b) Contents (Continued)  (3) Maximum weight of contents (Continued) 
  (ii) Inner Container Table 4. Maximum Weight of Inner Container Contents  Content Type Maximum Weight lbs. Dunnage  500 Group 1-Shielded Device  3,500 Group 3-Shielded Device  3,500  The maximum weight of the shielded device includes the mass of radioactive material and the source drawer.  (iii) The total fissile mass limit for the 435-B package is 15 grams.  (4) Maximum decay heat:  (i) For the contents described in Condition No. 5.(b)(2)(i), the maximum decay heat shall not exceed 200 watts per package.
(ii) For the contents described in Condition No. 5.(b)(2)(ii), the maximum decay heat shall not exceed 30 watts per package. 6. Plutonium sources are not permitted for transport by air.
: 7. Americium sources are not permitted for transport by air. 8. 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 Operating Procedures in Chapter 7 of the application; and  (b) The package must meet the Acceptance Tests and Maintenance Program of Chapter 8 of the application. 
: 9. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17. 
: 10. Revision No. 1 of this certificate may be used until January 31, 2019. 11. Expiration date:  July 31, 2019.


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   9355 2 71-9355 USA/9355/B(U)-96 6 OF 6   REFERENCES  National Nuclear Security Administration application dated April 27, 2017. Supplements dated: November 9, 2017. FOR THE U.S. NUCLEAR REGULATORY COMMISSION                    /RA John McKirgan Acting for/                    Meraj Rahimi, Acting Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety          and Safeguards 
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 9355                         2             71-9355           USA/9355/B(U)-96                 4  OF   6 5.(b)      Contents (Continued)
(2)      Maximum quantity of material per package (Continued)
(ii)    Inner Container-Shielded Devices Table 3. Maximum Activity and Weight of Shielded Devices 1 Maximum              Nominal            Sealed Source Model Name/Type                          Activity          Weight 2          Device Registry Ci                  lbs.                No.2 Group 1 Devices Gammator 50B, B, B34, G-50-B                          420                1,800          NR-0880-D-802-S Gammator M34                                        1,920                1,850          NR-0880-D-806-S Gammator M38                                        3,840                2,250          NR-0880-D-806-S Gammacell 1000 (GC-1000)                            3,840                2,800        NR-0880-D-808-S,
                      -Models A through D                          (bounding value)                          NR-1307-D-102-S
                      -Elite A through D, Type I and Type II Gammacell 3000 (GC-3000)                            3,048                3,300          NR-1307-D-102-S
                      -Elan A through C, Type I and Type II Group 3 Devices Gammacell-40 (GC-40 Exactor)                        2,250 3              2,650          NR-1307-D-101-S Notes:
: 1. Radionuclide in all cases is 137Cs.
: 2. Consult NRCs Sealed Source Device Registry for design and safety features of each model.
: 3. GC-40 activity is given for one of the two device components that make up a complete GC-40. Only one device component may be shipped at one time.
(3)    Maximum weight of contents (i)      LTSS For the LTSS, the payload of isotopes other than plutonium is limited by the activity rather than their weight.


Date: _1/26/18___  
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 9355                          2              71-9355        USA/9355/B(U)-96                5 OF    6 5.(b)      Contents (Continued)
(3)      Maximum weight of contents (Continued)
(ii)    Inner Container Table 4. Maximum Weight of Inner Container Contents Maximum Weight Content Type lbs.
Dunnage                        500 Group 1-Shielded Device                3,500 Group 3-Shielded Device                3,500 The maximum weight of the shielded device includes the mass of radioactive material and the source drawer.
(iii)    The total fissile mass limit for the 435-B package is 15 grams.
(4)      Maximum decay heat:
(i)      For the contents described in Condition No. 5.(b)(2)(i), the maximum decay heat shall not exceed 200 watts per package.
(ii)    For the contents described in Condition No. 5.(b)(2)(ii), the maximum decay heat shall not exceed 30 watts per package.
: 6.          Plutonium sources are not permitted for transport by air.
: 7.          Americium sources are not permitted for transport by air.
: 8.          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 Operating Procedures in Chapter 7 of the application; and (b)      The package must meet the Acceptance Tests and Maintenance Program of Chapter 8 of the application.
: 9.          The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.
: 10.        Revision No. 1 of this certificate may be used until January 31, 2019.
: 11.        Expiration date: July 31, 2019.
 
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 9355                  2                71-9355        USA/9355/B(U)-96                6 OF    6 REFERENCES National Nuclear Security Administration application dated April 27, 2017.
Supplements dated: November 9, 2017.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
                                                          /RA John McKirgan Acting for/
Meraj Rahimi, Acting Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards Date: _1/26/18___}}

Latest revision as of 16:39, 3 February 2020

Enclosure 1: Certificate of Compliance No. 9355, Revision No. 2 (Letter to A. M. Al-Daouk Revision No. 2 of Certificate of Compliance No. 9355 for the Model No. 435-B Transportation Package)
ML18026A875
Person / Time
Site: 07109355
Issue date: 01/26/2018
From: Meraj Rahimi
Spent Fuel Licensing Branch
To: Al-Daouk A
US Dept of Energy (DOE)
Allen W
Shared Package
ML18026A874 List:
References
EPID L-2017-LLA-0053
Download: ML18026A875 (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 9355 2 71-9355 USA/9355/B(U)-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 National Nuclear Security Administration National Nuclear Security Administration application P.O. Box 5400 dated April 27, 2017, as supplemented.

Albuquerque, NM 87185

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 No.: 435-B (2) Description The Model No. 435-B package consists of multiple configurations. The package is a Category I container. When loaded and prepared for transport, the external dimensions of the 435-B package are approximately 83 inches (in.) (210.8 centimeters (cm)) tall and 70 in. (177.8 cm) in diameter (over the lower impact limiter). The maximum weight of the package is 10,100 pounds (lbs) (4,545.5 kilograms (kg)).

Unless noted in the application, all elements of the 435-B package are made of Type 304 stainless steel in conformance with the American Standards for Testing Materials (ASTM) A240. The major components of the package include:

(i) A baseThe base consists of the lower torispherical head, lower flange, lower internal impact limiter, and external impact limiter. The volume inside the external impact limiter is filled with 15 pounds per cubic feet (lb/ft3) polyurethane foam poured in place. The inside surface of the bottom shell is covered with a 1/4-inch thick layer of refractory insulation paper. A full penetration weld connects the lower torispherical head (1/2-inch thick plate) to the lower flange.

(ii) A bellThe bell consists of the upper torispherical head, cylindrical shell, upper flange, vent and test port blocks, upper internal impact limiter, dual side thermal shield, head thermal shield, and the closure bolt access tube structure. Two, 1/4-inch thick, layers of refractory insulation paper cover the area of the containment wall adjacent to the tubes. Machined blocks of 30 lb/ft3 polyurethane foam are located between the tubes.

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 9355 2 71-9355 USA/9355/B(U)-96 2 OF 6 5.(a) Packaging (Continued)

(2) Description (iii) An internal lodgment, made of aluminum, which supports the Long Term Storage Shield (LTSS)The lodgment and the inner container designs allow maintaining the position of the payload in the package cavity during normal conditions of transport and hypothetical accident conditions. The LTSS rests on a 1/2-inch thick plate covered with a 1/2-inch thick layer of neoprene rubber.

(iv) LTSSThe LTSS consists of a central steel magazine, or barrel, surrounded by thick lead encased in a steel shell. The barrel contains four longitudinal holes, each of which can accommodate one drawer assembly.

(v) An inner container, which supports shielded devicesThe inner container holds a shielded device and provides support for the device and the blocking (dunnage) materials during transport.

(vi) Two internal impact limitersThe internal impact limiters located at each end of the payload cavity include an array of 130 ASTM A249 or A269, Type TP304, stainless steel tubes. The impact limiters are curved on one side to match the inside of the torispherical head, and flat on the other. Each of the 130 tubes is tack-welded in three places to a stainless steel tube stabilizer sheet. Four stainless steel clips welded to the inner surface of the containment boundary in the lower and upper position hold the internal impact limiters in place.

The LTSS or shielded devices provide shielding. Shielding materials are lead, tungsten, steel, or depleted uranium. The LTSS provides the shielding for the sealed capsule content specified in Tables 1 and 2. Therefore, these sources must be packed in the LTSS drawer(s). The shielded devices, identified in Table 3, are self-shielding, and must be packed in an inner container for shipment as specified in Table 4.

(3) Drawings The packaging is constructed in accordance with AREVA Federal Services LLC drawings:

1) 1916-01-01-SAR, 435-B Package Assembly SAR Drawing, sheets 1-7, Revision 6
2) 1916-01-02-SAR, 435-B LTSS Lodgment SAR Drawing, sheets 1-2, Revision 4
3) 1916-01-03-SAR, 435-B Inner Container SAR Drawing, sheets 1-2, Revision 4 5.(b) Contents (1) Type and form of material Radioactive sealed sources of isotopes described in Tables 1 and 2.

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 9355 2 71-9355 USA/9355/B(U)-96 3 OF 6 5.(b) Contents (Continued)

(2) Maximum quantity of material per package (i) LTSS Table 1. Maximum Activity of LTSS Payload Source Nuclides 1, 2 Maximum Activity Nuclide Ci 60Co 12,970 137Cs 14,000 90Sr 1,000 241Am (no Be) 3 1,000 241Am Be 3 6.6 192Ir 200 75Se 80 Notes:

1. Physical form of all nuclides is solid material in a sealed capsule.
2. The maximum activity listed is the maximum for a single nuclide in the LTSS. For combinations of different nuclides, lower activity limits apply as discussed in Chapter 5, Shielding Evaluation, and Operating Procedures in Chapter 7 of the application.
3. Impurities may include oxygen and chlorine.

Table 2. Maximum Mass of LTSS Payload Source Nuclides. 1, 2 Maximum Mass Nuclide grams of Pu 238Pu (no Be) 75 g Pu 239Pu (no Be) 15 g Pu 239Pu Be 15 g Pu Notes:

1. Physical form of all nuclides is solid material in a sealed capsule.
2. Impurities may include oxygen.

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 9355 2 71-9355 USA/9355/B(U)-96 4 OF 6 5.(b) Contents (Continued)

(2) Maximum quantity of material per package (Continued)

(ii) Inner Container-Shielded Devices Table 3. Maximum Activity and Weight of Shielded Devices 1 Maximum Nominal Sealed Source Model Name/Type Activity Weight 2 Device Registry Ci lbs. No.2 Group 1 Devices Gammator 50B, B, B34, G-50-B 420 1,800 NR-0880-D-802-S Gammator M34 1,920 1,850 NR-0880-D-806-S Gammator M38 3,840 2,250 NR-0880-D-806-S Gammacell 1000 (GC-1000) 3,840 2,800 NR-0880-D-808-S,

-Models A through D (bounding value) NR-1307-D-102-S

-Elite A through D, Type I and Type II Gammacell 3000 (GC-3000) 3,048 3,300 NR-1307-D-102-S

-Elan A through C, Type I and Type II Group 3 Devices Gammacell-40 (GC-40 Exactor) 2,250 3 2,650 NR-1307-D-101-S Notes:

1. Radionuclide in all cases is 137Cs.
2. Consult NRCs Sealed Source Device Registry for design and safety features of each model.
3. GC-40 activity is given for one of the two device components that make up a complete GC-40. Only one device component may be shipped at one time.

(3) Maximum weight of contents (i) LTSS For the LTSS, the payload of isotopes other than plutonium is limited by the activity rather than their weight.

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 9355 2 71-9355 USA/9355/B(U)-96 5 OF 6 5.(b) Contents (Continued)

(3) Maximum weight of contents (Continued)

(ii) Inner Container Table 4. Maximum Weight of Inner Container Contents Maximum Weight Content Type lbs.

Dunnage 500 Group 1-Shielded Device 3,500 Group 3-Shielded Device 3,500 The maximum weight of the shielded device includes the mass of radioactive material and the source drawer.

(iii) The total fissile mass limit for the 435-B package is 15 grams.

(4) Maximum decay heat:

(i) For the contents described in Condition No. 5.(b)(2)(i), the maximum decay heat shall not exceed 200 watts per package.

(ii) For the contents described in Condition No. 5.(b)(2)(ii), the maximum decay heat shall not exceed 30 watts per package.

6. Plutonium sources are not permitted for transport by air.
7. Americium sources are not permitted for transport by air.
8. 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 Operating Procedures in Chapter 7 of the application; and (b) The package must meet the Acceptance Tests and Maintenance Program of Chapter 8 of the application.

9. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.
10. Revision No. 1 of this certificate may be used until January 31, 2019.
11. Expiration date: July 31, 2019.

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 9355 2 71-9355 USA/9355/B(U)-96 6 OF 6 REFERENCES National Nuclear Security Administration application dated April 27, 2017.

Supplements dated: November 9, 2017.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION

/RA John McKirgan Acting for/

Meraj Rahimi, Acting Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards Date: _1/26/18___

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