ML19190A150
| ML19190A150 | |
| Person / Time | |
|---|---|
| Site: | 07109796 |
| Issue date: | 07/05/2019 |
| From: | John Mckirgan Spent Fuel Licensing Branch |
| To: | Plate N US Dept of Energy, Naval Reactors |
| White B | |
| Shared Package | |
| ML19190A147 | List: |
| References | |
| EPID L-2019-RNW-0013 | |
| Download: ML19190A150 (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 9796 2 71-9796 USA/9796/B(U)F-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 U. S. Department of Energy Core Independent M-290 Safety Analysis Report for Division of Naval Reactors Packaging," dated May 13, 2013, as supplemented Washington, D.C. 20585
- 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.: M-290 (2) Description The M-290 is a right circular cylinder for transporting spent fuel. The package's approximate dimensions and weights are as follows:
Cavity diameter 71 inches Cavity height 242 inches Body outer diameter, upper section 92.15 inches lower section 96.15 inches Body steel wall thickness, upper section 10.6 inches lower section 12.6 inches Maximum outer diameter 128 inches Maximum height (including domes) 361.5 inches Maximum weight (including contents) 520,000 pounds The M-290 package body is fabricated primarily from dual-certified Type 304/304L stainless steel forgings, with the upper portion fabricated from a forging constructed of Nitronic 40. All forgings are joined via full-penetration welds. The upper inside wall of the package body includes two grooves (one for engagement of an internal retaining ring, and the other for
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 9796 2 71-9796 USA/9796/B(U)F-96 2 OF 5 5.(a)(2) Description (continued) engagement of a closure shear ring system). Between these grooves is a seating ledge for the closure head or canister restraint plate. The package bottom plate is approximately 11.56 inches thick. The thicker lower region of the package body is encircled by a set of 50, equally-spaced, thermal fins welded to the exterior surface. The upper and lower regions of the package body include exterior flanges into which impact mitigating, top and bottom domes are engaged during shipment.
The M-290 container body has no penetrations other than the main top opening, which is sealed during transport via a 5-inch thick, Nitronic 40 containment cover. The containment cover includes three, concentric O-rings, and is attached to the package body using 30 high-strength fasteners. Penetrations in the containment cover (for leak testing or venting operations) are plugged and sealed prior to transport.
Each end of the M-290 includes a large, impact mitigating dome that is also used for attachment of package handling hardware. The domes are fabricated from Type 304 stainless steel and are engaged in grooves in the package body. The top dome is attached via a set of 24 high-strength fastening pins; the bottom dome is attached via a set of 12 retention wedges, each of which is attached via two high-strength fasteners. The domes are custom-designed to reduce package loadings and protect the upper containment seals under accident conditions.
The M-290 employs two categories of spent fuel internals: direct-loaded and canistered.
Direct-loaded spent fuel configurations include an internal assembly installed directly in the M-290 package and held in place via an internal retaining ring (engaged in the package wall groove). Direct-loaded spent fuel shipments also include a thick closure head that seats on the internal package ledge and includes an access port for installation and removal of the spent fuel. The access port is closed and sealed via a bolted access plug. The head and plug each include supplemental O-ring seals.
Canistered configurations include a separate, sealed canister in which the spent fuel is located (within unique internals inside the canister). The canister is restrained within the M-290 utilizing a canister restraint installed in the same region occupied by the closure head for non-canistered configurations. The closure head (or canister restraint) is restrained and preloaded via a segmented shear ring that engages in the upper package body groove. The shear ring system is engaged in the groove and preloaded via a set of 28 shear ring jack screws. The shear ring is further prevented from disengagement via a backing ring bolted to the closure head or canister restraint.
Each M-290 is shipped at a 1-degree tilt (with the closure end upward) on a specially-designed railcar. The center of the package body sits within a custom shipping cradle (welded to the railcar deck), and cradle caps (which gird the upper portion of the body) provide vertical restraint. Two reaction pads (one at each end of the package) provide additional vertical support to the package.
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 9796 2 71-9796 USA/9796/B(U)F-96 3 OF 5 5.(a)(3) Drawings The packaging is constructed and assembled in accordance with the drawings in Appendix 1.3.3 of the M-290 application, the safety analysis report for packaging (SARP). Internals assemblies and fuel modules for the A1W and A1G spent fuel are constructed and assembled in accordance with drawings in Appendix 1.3.3 of the A1W and A1G SARPs, respectively.
5.(b) Contents (1) Type and form of material Spent fuel, limited to the following types, including associated activated corrosion products:
(i) A1W spent fuel modules.
(ii) A1G spent fuel modules (2) Maximum quantity of material per package Total package weight, including spent fuel, canister and internals, not to exceed 520,000 pounds, and (i) For contents described in 5(b)(1)(i):
Authorized fuel loadings, internals assembly, and other loading restrictions are specified in the A1W SARP. A1W spent fuel modules, not to exceed 14,730 Btu/hr decay heat per package at the time of canister draining.
(ii) For contents described in 5(b)(1)(ii):
Authorized fuel loadings, internals assembly, and other loading restrictions are specified in the A1G SARP. The A1G spent fuel modules decay heat shall not exceed 58,484 Btu/hr decay heat per package at the time draining the M-290 package.
(c) Criticality Safety Index 0
- 6. In addition to the limitations above, the A1W fuel is limited to:
(a) The A1W modules are packaged with internals inside one A1W canister in the M-290 packaging.
(b) Shipment shall be made no earlier than 730 days after shutdown.
(c) The A1W canister draining shall occur no earlier than 805 days after shutdown, or at a time after shutdown as determined from applicable safety analyses.
(d) Module Installation Lifting Adapters must be installed on all A1W modules and Control Rod Locking Devices must be installed in all modules with control rods.
(e) The A1W core age must be per Section 1.2.5 of the A1W SARP.
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 9796 2 71-9796 USA/9796/B(U)F-96 4 OF 5 (f) The loaded A1W canister inside the M-290 shipping container must not be sealed for greater than 30 years.
(g) The package must contain no more than 7 gallons of residual water.
- 7. In addition to the limitations above, the A1G fuel is limited to:
(a) The A1G modules are packaged with internals inside the M-290 packaging.
(b) Shipment of the A1G spent fuel modules shall not occur earlier that 270 days after shutdown.
(c) Defueling grapple adaptors must be installed on all A1G spent fuel modules, and all modules must have control rods.
(d) Control rod hold-down assemblies must be installed on applicable A1G spent fuel modules as identified in Section 1.2.5 of the A1G SARP, with the exception that control rod hold-down assemblies are not required for the A1G modules from the cored identified in Chapter A1 of the A1G SARP Addendum.
(e) The A1G core age and fuel type must be per Section 1.2.5 of the A1G SARP, with its addendum.
(f) The M-290 package loaded with A1G spent fuel modules must not be sealed for longer than 75 years.
- 8. Failed fuel or fuel with defective cladding is not authorized for shipment.
- 9. Each packaging must meet the Acceptance Tests and Maintenance Program of Chapter 8 of the application, as supplemented.
- 10. The package must be prepared for transport and operated in accordance with Chapter 7 of the application, as supplemented.
- 11. Transport by air of fissile material is not authorized.
- 12. Expiration date: December 31, 2024.
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 9796 2 71-9796 USA/9796/B(U)F-96 5 OF 5 REFERENCES "Core Independent M-290 Safety Analysis Report for Packaging," dated May 13, 2013.
Supplements dated March 31, May 20 and June 30, 2014; May 18, 2017; and May 9, 2019.
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: 7/5/19