ML20035F187
| ML20035F187 | |
| Person / Time | |
|---|---|
| Site: | 07109321 |
| Issue date: | 01/30/2020 |
| From: | Dan Doyle Office of Nuclear Material Safety and Safeguards |
| To: | EnergySolutions, EnergySolutions |
| PSaverot NMSS/DFM/STL 415.7505 | |
| Shared Package | |
| ML20035F184 | List: |
| References | |
| EPID L-2020-RNW-0004 | |
| Download: ML20035F187 (5) | |
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 9321 3 71-9321 USA/9321/B(U)-96 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
- a. ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION EnergySolutions EnergySolutions application, Revision No. 3, dated July 740 Osborn Road 27, 2010, as supplemented.
Barnwell, SC 29812.
- 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.: 3-60B (2) Description A cylindrical austenitic stainless steel and lead shielded packaging for shipment of Type B quantities of radioactive waste materials. The packaging is transported in the horizontal position in a shipping cradle where it is supported and tied down by its four trunnions.
Trunnions are structural parts of the packaging.
Approximate dimensions and weights are as follows:
Packaging Height 125-5/8 inches Packaging Outer Diameter 51-1/2 inches Packaging Cavity Height / Diameter 109-3/8 inches / 35 inches Overall Package Height, with impact limiters 165 inches Overall Package Diameter, with impact limiters 82 inches Package Total Gross Weight 80,000 lbs Maximum Total Weight of Contents, Secondary Containers and Cavity Spacers 9,500 lbs
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 9321 3 71-9321 USA/9321/B(U)-96 2 OF 5 5.(a)(2) Description (Continued)
The packaging has two configurations: Configuration A and Configuration B. For both configurations, the packaging body consists of a 1 1/4-inch thick external stainless steel shell (ASTM A-240, Type 304L) and a 3/4-inch thick internal stainless steel shell. The annular space between the inner and outer shells is filled with a 6-inch thick layer of lead (ASTM B-29 chemical copper). A 12-gauge stainless steel (Type 304 L) thermal shield is welded to the exterior of the external shell to provide protection during hypothetical accident fire condition events.
The lid is constructed of several circular stainless steel plates welded together for a total thickness of 10 1/2 inches. Lid Configuration A is sealed by a pair of elastomer O-rings within a seal ring fabricated from austenitic stainless steel. The seal ring is partially recessed within a machined groove on the inside surface of the outer lid and welded in place. Lid Configuration B is sealed using three elastomer O-rings which are placed into grooves machined directly into the outer lids inner surface. The middle O-ring serves as the containment boundary and the inner and outer O-rings serve as O-ring seal test boundaries.
In both Configuration A and Configuration B, a bolting ring provides sealing and bolting surfaces for the lid at the top end of the packaging. Sixteen equally spaced 1 1/2-inch diameter bolts are used to secure both lid configurations.
Both lid configurations have test ports for performing periodic and pre-shipment leak testing.
Periodic and pre-shipment leak-testing is accomplished in the Configuration A lid by two diametrically opposed test ports which penetrate the seal ring plate between the O-rings.
Periodic and pre-shipment leak-testing is accomplished in the Configuration B lid by four test ports. Two diametrically opposed test ports are located between the inner test O-ring and the middle containment O-ring, and two diametrically opposed test ports are located between the outer test O-ring and the middle containment O-ring.
In addition, both lid configurations have a vent port plug assembly to assist in draining water from the cask cavity. There are two vent port plug assembly configurations: Configuration A and Configuration B. Both configurations utilize a cover plate, a steel rod and two O-rings.
For the Configuration A vent port plug assembly, grooves are machined into a seal ring to hold the two O-rings. The seal ring is fabricated as a separate piece and welded to the cover plate. In addition, the steel rod penetrates the Configuration A vent port cover plate. For the Configuration B vent port plug assembly, the O-rings are held in place by grooves machined directly into the cover plate, and the steel rod does not penetrate the cover plate. Six 1/2-inch diameter hex head bolts are used to secure both vent port plug assembly configurations to the lid.
The bottom end of the packaging consists of an external circular 3-inch thick stainless steel plate, a 5-inch thick lead shield, and a 3/4-inch inner containment baseplate. In Configuration A, a bottom corner forging is welded both to the 1 1/4-inch external shell plate and to the 3-inch plate. In Configuration B, the 3-inch plate is welded directly to the 1 1/4-inch external shell plate. Both Configuration A and Configuration B of the packaging employ a drain port
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 9321 3 71-9321 USA/9321/B(U)-96 3 OF 5 which is fabricated from either a single piece of austenitic stainless steel or two pieces of austenitic stainless steel joined by a full penetration weld. There are two drain port configurations which are identical except that the Configuration B drain port includes a threaded hole on the cavity side of the drain port. A set screw protects the Configuration B drain port threads and provides contamination control. The containment boundary is defined as the inner shell of the packaging body, the inner baseplate, the lid, the primary lid bolts, either the Configuration A inner O-ring or the Configuration B middle O-ring, and the vent and drain port plugs.
Cylindrical impact limiters extend approximately 15 inches beyond the outside wall of the packaging, and are constructed of fully welded stainless steel shells filled with a crushable foamed-in-place closed-cell rigid polyurethane foam with specifications described in the application.
(3) Drawings The packaging is constructed and assembled in accordance with EnergySolutions Drawing No. C-002-165024-001, sheets 1-10, Rev. 5.
5.(b) Contents (1) Type and form of material (a) Byproduct, source, and special nuclear material in the form of inorganic solids, inorganic solidified material, and inorganic resins.
(b) Radioactive material in the form of activated and/or contaminated non-fuel bearing reactor or accelerator components or segments of components.
(2) Maximum quantity of material per package (a) 1110 TBq (30,000 Ci) of Co-60 or equivalent. Equivalency to other radionuclides is determined by the total energy and its spectrum.
(b) Decay heat of contents must not exceed 500 watts. For contents with residual water, the total decay heat must not exceed 4.46 times the volume fraction divided by the mass fraction of water in the contents.
(c) Contents may include fissile material in compliance with the mass limits of 10 CFR 71.15. Any contents that contain more than 0.74 TBq (20 Ci) of plutonium must be in solid form.
(d) The specific activity of radioactive powdered or dispersible solids shall not exceed 330 Ci/gram of Co-60 or equivalent.
(e) Materials that auto-ignite or change phase below 350ºF, not including water, shall not be included into the contents.
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 9321 3 71-9321 USA/9321/B(U)-96 4 OF 5 (f) Total weight of contents, including shoring and secondary containers, must not exceed 9,500 pounds.
- 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 Chapter 7 of the application.
(b) The package shall meet the acceptance tests and be maintained in accordance with Chapter 8 of the application.
- 7. Contents shall be packaged in secondary containers.
- 8. Contents shall be placed such that the center of gravity of the package is at approximately the same location as the geometric center of the package - approximately the same location being defined as having a +/-10% difference in distance of the cavity inside dimensions from the geometric center of the package in any direction.
- 9. Shoring must be placed between the secondary container and the packaging cavity to prevent movement during accident conditions of transport.
- 10. Flammable gas (hydrogen) concentration is limited to less than 5 % in volume. Inerting is not allowed to limit the concentration of flammable gases.
- 11. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.
- 12. Revision No. 2 of this certificate may be used until February 28, 2021.
- 13. Expiration date: September 30, 2025.
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 9321 3 71-9321 USA/9321/B(U)-96 5 OF 5 REFERENCES EnergySolutions application Safety Analysis Report for the Model No. 3-60B Type B Shipping Cask, Revision No. 3, dated July 27, 2010.
Supplements dated: January 31, April 4, July 31, and November 24, 2014, and January 19 and July 15, 2015.
Renewal request letter dated January 30, 2020.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
/RA/
Daniel I. Doyle, Acting Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Date: February 7, 2020.