ML25112A303
| ML25112A303 | |
| Person / Time | |
|---|---|
| Site: | 07109403 |
| Issue date: | 04/30/2025 |
| From: | Yoira Diaz-Sanabria Storage and Transportation Licensing Branch |
| To: | NAC International |
| Shared Package | |
| ML25112A301 | List: |
| References | |
| EPID L-2023-NEW-0007 | |
| Download: ML25112A303 (1) | |
Text
2RC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATION NUMBER 9403
- b. REVISION NUMBER 0
- c. DOCKET NUMBER 71-9403
- d. PACKAGE IDENTIFICATION NUMBER USA/9403/B(U)-96 PAGE PAGES 1 OF 5
- 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.
- c.
ISSUED TO (Name and Address)
NAC International 2 Sun Court, Suite 220 Peachtree Corners, GA 30092
- d.
TITLE AND IDENTIFICATION OF REPORT OR APPLICATION NAC International Volunteer Package Safety Analysis Report, Revision No. 0, dated April 2025.
- 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: Volunteer (2)
Description The Volunteer packaging is comprised of a cask assembly, with identical upper and lower impact limiters, and internal support structures for specific contents to be shipped.
The packaging has three (3) different length configurations (i.e., long, standard, and short) of 266.5-inch, 254.5-inch, and 206.5-inch, respectively. The cask cavity dimensions of the long, standard, and short cask configurations are Ø 26.5-inch by 180.5-inch, Ø 26.5-inch by 168.5-inch, and Ø 26.5-inch by 120.5-inch, respectively.
The cask body consists of a 1.25-inch-thick stainless-steel inner shell, surrounded by a 4.54-inch-thick (minimum) lead gamma shield and a 2.25-inch-thick stainless-steel outer shell.
The outside of the cask body weldment, between the end regions that are covered by the impact limiters, is covered by a 1/8-inch-thick stainless-steel thermal shield that is offset from the outer shell by 1/8-inch-thick spacers and a wire wrap to create an insulating air gap.
The top and bottom ends of the cask assembly both include a total thickness of 9.0 inches of stainless steel. The inner shell is welded to a stainless-steel flange at the top end and a stainless-steel inner bottom plate (forging) at the bottom end.
2RC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATION NUMBER 9403
- b. REVISION NUMBER 0
- c. DOCKET NUMBER 71-9403
- d. PACKAGE IDENTIFICATION NUMBER USA/9403/B(U)-96 PAGE PAGES 2 OF 5
5.(a)(2)
Description (continued)
The outer shell is welded to the stainless-steel flange at the top end and a stainless-steel outer bottom forging at the bottom end. The inner bottom plate fits within a machined 3.0-inch-deep pocket on the inside of the outer bottom forging to provide 9.0 inches of stainless-steel shielding on the bottom end.
The cask lid is a 9.0-inch-thick stainless-steel stepped design, secured to the cask body weldment by twenty-four (24) 11/2-inch diameter bolts.
The cask assembly includes a vent port in the cask lid and a drain port in the flange, both sealed with identical port covers that are secured to the cask assembly by three (3) 7/8-inch diameter bolts.
Elastomeric cask containment seals are used on the cask lid and port cover plates for all cask configurations except for tritium producing burnable absorber rod (TPBAR) contents, which use metallic containment seals. Elastomeric test O-ring seals are provided outside the containment seals for leak testing.
All package configurations have an 86.0-inch outside diameter, excluding impact limiter lift lugs and support angles. The cask assembly diameter is 43.0-inch at the top and bottom ends where the impact limiters are attached, and 43.5-inch in the region between the upper and lower impact limiters (excluding the upper and lower trunnions). The overall length of the long, standard, and short cask assemblies is 198.5-inch, 186.5-inch, and 138.5-inch, respectively.
The packaging is equipped with identical cylindrical cup-shaped upper and lower impact limiters that fit over the respective ends of the cask assembly. Each impact limiter secured to the cask assembly by eight (8) 1-inch diameter threaded retaining rods, washer plates, and hex nuts. The impact limiters are constructed from Type 304 stainless-steel shells that completely encase the internal balsa wood cores and protect them from the external environment. Each impact limiter assembly is Ø 86.0-inch by 49.0-inch long, with a Ø 43.4-inch by 15.0-inch-deep pocket that fits over the end of the cask assembly.
The maximum weight of the contents and internal support structures is 11,500 lbs. for all cask configurations. The maximum gross weight of the package for the long, standard, and short configurations is approximately 84.4 kip, 80.5 kip, and 64.8 kip, respectively.
2RC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATION NUMBER 9403
- b. REVISION NUMBER 0
- c. DOCKET NUMBER 71-9403
- d. PACKAGE IDENTIFICATION NUMBER USA/9403/B(U)-96 PAGE PAGES 3 OF 5
5.(a)(3)
Drawings The package shall be constructed and assembled in accordance with the following NAC International Drawing numbers:
Drawing No.
Revision Drawing Title 70000.38-L100 1P Packaging Assembly, Volunteer 70000.38-L110 1P Cask Assembly, Volunteer 70000.38-L115 2P Port Cover Assembly, Volunteer 70000.38-L116 1P Port Cover Assembly, Metal Seal, Volunteer 70000.38-L120 2P Cask Body Weldment, Volunteer 70000.38-L130 3P Cask Lid Assembly, Volunteer 70000.38-L131 2P Cask Lid Assembly, Metal Seal, Volunteer 70000.38-L141 0P Impact Limiter, Volunteer 70000.38-L150 0P Shield Liner Assembly, Volunteer 70000.38-L160 0P TPBAR Basket Assembly, Volunteer 70000.38-L165 0P TPBAR Spacer, Volunteer 70000.38-L166 0P TPBAR Bearing Plate, Volunteer 70000.38-L167 0P Basket Extension Assembly, TPBAR, Volunteer 5(b)
Contents (1)
Type and Form of Material (a)
Irradiated Hardware: Radioactive material in the form of neutron activated metals or metal oxides in solid form, and/or contaminated non-fuel bearing reactor accelerator components, intact, segmented, and/or sized reduced, and contained inside a shield liner assembly.
(b)
Vitrified High-Level Waste (HLW): Radioactive waste material confined within a solidified borosilicate glass matrix and contained inside a sealed stainless-steel HLW canister with a welded closure.
(c)
TPBARs: Production TPBARs in consolidation canisters.
2RC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATION NUMBER 9403
- b. REVISION NUMBER 0
- c. DOCKET NUMBER 71-9403
- d. PACKAGE IDENTIFICATION NUMBER USA/9403/B(U)-96 PAGE PAGES 4 OF 5
5(b)
Contents of Packaging (2)
Maximum quantity of material per package:
(a)
Irradiated Hardware (i)
Maximum Co-60 activity of 30,000 Ci.
(ii)
Maximum heat load of 470 thermal watts per package.
(b)
Vitrified HLW i)
Maximum combined total activities of all gamma and neutron-emitting isotopes not exceeding 474 Ci/kg and 2.15 Ci/kg, respectively. Maximum combined total activity density of Ba-137m and Cs-137 not to exceed 350 Ci/kg.
ii)
Maximum linear heat generation rate of 25.2 watts per inch of canister length, and maximum total heat load not to exceed 4.79 kW for a 15-foot long HLW canister and 2.75 kW for a 10-foot long HLW canister.
(c)
TPBAR i)
Up to 4 consolidation canisters, each with no more than 300 TPBARs, not to exceed 1,200 TPBARs total per shipment and no more than two (2) pre-failed TPBAR per shipment.
ii)
Average tritium content shall not exceed 1.5g per TPBAR.
iii)
Minimum cooling time of 60 days.
iv)
Maximum decay heat of 2.75 watts per TPBAR and 3.30 kW per package.
(d)
Plutonium contents in quantities greater than 0.74 TBq (20 Ci) must be in solid form.
(e)
Fissile content shall meet 10 CFR 71.15 fissile exempt limits 5(c)
Criticality Safety Index (CSI): 0 (Not Applicable).
- 6.
In addition to the requirements of Subpart G of 10 CFR Part 71, the package shall:
(a)
Be prepared for shipment and operated in accordance with the Operating Procedures in Chapter 8, and (b)
Be tested and maintained in accordance with the Acceptance Tests and Maintenance Program in Chapter 9 of the application.
2RC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
- 1. a. CERTIFICATION NUMBER 9403
- b. REVISION NUMBER 0
- c. DOCKET NUMBER 71-9403
- d. PACKAGE IDENTIFICATION NUMBER USA/9403/B(U)-96 PAGE PAGES 5 OF 5
- 7.
Additional operating requirements of the package include:
(a)
Transport by air is not authorized.
(b)
The package is transported in an exclusive-use conveyance only.
- 8.
The package must be marked with Package Identification Number USA/9403/B(M)-96 for shipments of TPBAR contents.
- 9.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.
- 10.
Expiration Date: May 31, 2030.
REFERENCES NAC International Volunteer Package Safety Analysis Report Revision No. 0 dated April 2025.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Yoira Diaz-Sanabria, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Date: April 30, 2025 YOIRA DIAZ-SANABRIA Digitally signed by YOIRA DIAZ-SANABRIA Date: 2025.04.30 16:58:55 -04'00'