ML24239A812
| ML24239A812 | |
| Person / Time | |
|---|---|
| Site: | 07109796 |
| Issue date: | 02/08/2024 |
| From: | Plate N US Dept of Energy, Naval Reactors |
| To: | John Lubinski Office of Nuclear Material Safety and Safeguards |
| References | |
| Download: ML24239A812 (1) | |
Text
CONFIDENTIAL//RESTRICTED DATA RESTRICTED DATA This document contains Restricted Data as defined in the Atomic Energy Act of 1954, as amended. Unauthorized disclosure is subject to administrative and criminal sanctions.
Classified By:
N. S. Plate - Nuclear Engineer Derived From: DOE-DOD CG-RN1 Rev 3 Feb 1996, DOE OC CONFIDENTIAL//RESTRICTED DATA NR:RR:JHKampen G#C24-00734 08 Feb 2024 Handle as UNCLASSIFIED when enclosures (1) & (2) are removed.
John Lubinski Director, Office of Nuclear Material Safety and Safeguards Nuclear Regulatory Commission Washington, DC 20555 M-290 SHIPPING CONTAINERA1G SPENT NUCLEAR FUEL SAFETY ANALYSIS REPORT FOR PACKAGING; REQUEST FOR NUCLEAR REGULATORY COMMISSION REVIEW AND CONCURRENCE
Background:
The M-290 shipping container is used to transport aircraft carrier spent nuclear fuel from the servicing facility to the Naval Reactors Facility in Idaho and will be used to transport spent fuel canisters from the Naval Reactors Facility to a geologic repository. The M-290 shipping container is designed to meet the Type B package requirements for shipment of fissile and highly radioactive material in accordance with Title 10, Code of Federal Regulations, Part 71 (10CFR71). Because the M-290 shipping container will ship a variety of fuel types, compliance with 10CFR71 is demonstrated through a combination of two Safety Analysis Reports for Packaging (SARPs): a core-independent SARP for aspects of the package that are common to all shipments and a core-dependent SARP for aspects that are unique to each fuel type or configuration.
Previous revisions of the core-dependent A1G Spent Fuel in the M-290 SARP evaluated spent fuel contents on a ship-specific basis.
Discussion: This letter forwards Revision 2 of the A1G Spent Nuclear Fuel in the M-290 SARP as Enclosure (2), which evaluates a wider subset of NIMITZ class cores to support refuelings and defuelings. When combined with the previously approved core-independent M-290 SARP, Enclosure (2) demonstrates that transport of A1G spent nuclear fuel in the M-290 shipping container meets the requirements of 10CFR71 for A1G spent fuel from cores installed in USS HARRY S. TRUMAN (CVN 75), USS RONALD REAGAN (CVN 76), USS GEORGE H. W. BUSH (CVN 77), USS NIMITZ (CVN 68), USS DWIGHT D. EISENHOWER (CVN 69), and USS CARL VINSON (CVN 70). Enclosure (1) provides a high level summary of the changes in Revision 2.
Enclosure (2) provides the tracked-changes version of Revision 2.
DEPARTMENT OF ENERGY NATIONAL NUCLEAR SECURITY ADMINISTRATION 1000 INDEPENDENCE AVENUE SW WASHINGTON DC 20585-1000 UNCLASSIFIED UNCLASSIFIED
UNCLASSIFIED 2
NR:RR:JHKampen G#C24-00734 UNCLASSIFIED Request for Action: Naval Reactors requests NRC review and concurrence with the A1G Spent Nuclear Fuel in the M-290 SARP, provided in Enclosure (2). Enclosure (3) provides requested changes to the NRC CoC for the M-290 (USA/9796/B(U)F-96). To support the start of the defueling/refueling sequence for CVN 75, Naval Reactors requests NRC schedule your review to complete by February 2025.
If you have any questions, please do not hesitate to call me at (202) 781-6034.
N. S. Plate Naval Reactors
Enclosures:
(1)
SUMMARY
OF CHANGES IN THE A1G SPENT NUCLEAR FUEL IN THE M-290 SHIPPING CONTAINER SAFETY ANALYSIS REPORT FOR PACKAGING (2) A1G SPENT FUEL IN THE M-290 SHIPPING CONTAINER SAFETY ANALYSIS REPORT FOR PACKAGING, REVISION 2 (3) REQUESTED CHANGES TO THE NRC CERTIFICATE OF COMPLIANCE FOR THE M-290 SHIPPING CONTAINER, USA/9796/B(U)F-96, REVISION 3 (DRAFT)
NTK: PRNR-REC, PRNR-REP Copy to (Electronic, without Enclosure (2) contents):
Distribution via ADSARS General Manager, NNL (Thomas Sambolt)
Executive Manager, RS.Reactor Servicing (RS), NNL (Vince Pantloni)
Executive Manager, RSS.Reactor Servicing Systems (RSS), NNL (Matt Drewen)
Subdivision Technical Manager, RSS.Shipping Containers, NNL (Suzanne Fiscus)
Unit Technical Manager, RSS.M-290/M-140 Design and Analysis, NNL (Donald Tezbir)
Mechanical Engineer, RSS.M-290/M-140 Design and Analysis, NNL (Shane Hallett)
Manager, NRLFO, NRLFO.Manager, NRLFO, NR (Jay Showman)
Hard copy distribution (next page)
Digitally signed by platens@nnpp.gov (1000013550)
Date: 2024.02.08 17:07:27 -05'00'
UNCLASSIFIED 3
NR:RR:JHKampen G#C24-00734 UNCLASSIFIED Hard Copy Distribution (with all enclosures):
Director, Division of Fuel Management, NMSS, NRC (S. Helton)
Chief, Storage and Transportation Licensing Branch, DFM, NMSS, NRC (Y. Diaz-Sanabria)
Senior Project Manager, STLB, DFM, NMSS, NRC (N. Devaser)
1 Enclosure (3) to NR:RR:JHKampen G#C24-00734 ENCLOSURE (3)
REQUESTED CHANGES TO THE NRC CERTIFICATE OF COMPLIANCE FOR THE M-290 SHIPPING CONTAINER, USA/9796/B(U)F-96, REVISION 3 (DRAFT)
Enclosed are recommended changes to the NRC Certificate of Compliance, showing additions and deletions from the latest revision (Revision 2) of the certificate.
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10CFR71 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 USN9796/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
\\P REGU 4.
CONDITIONS 1A This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71 as applicable, and thonditions 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 packages approximate dimensions and weights are as follows: /(
Cavity diameter/
t1J)j Cavity height 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 C,0 71 inches 242 inches 3
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 0-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.
j 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 hetd 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 0-ring seals.
V 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) 10CFR7I 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 USN9796/B(U)F-96 2
OF 5
3
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
- a. CERTIFICATE NUMBER
- b. REVISION NUMBER C. DOCKET NUMBER
- d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9796 2
71-9796 USN9796/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 AIW and Al G spent fuel are constructed and assembled in accordance with drawings in Appendix 1.3.3 of the A1W and Al G SARPs, respectively.
5.(b)
Contents (1)
Type and form of material Spent fuel, limited to the following types, including associated activated corrosion products:
(i)
AIW spent fuel modules.
RE (ii)
AIG spent fuel modules
?
(2)
Maximum quantity of material per package 0
Total package weight, including spent fuel, canister and internals, not to exceed 520,000 pounds, and C)
(i)
For contents described in 5(b)(l )(i):
0 II.
Authorized fuel loadings, internals assembly, and other loading restrictions are specified in the A1W SARP. AJW spent fuel modules, not to exceed 14,730 Btu/hr decay heat per package at the time of canister draining.
4 (ii)
For contents described in 5(b)(1 )(ii):
C, 1
(I4%*
Authorized fuel loadings, internals assembly, and other loading restrictions are specified in the Al G SARP. The Al G 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 AJW modules are packaged with internals inside one AIW canister in the M-290 packaging.
(b)
Shipment shall be made no earlier than 730 days after shutdown.
(c)
The AIW 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 AIW core age must be per Section 1.2.5 of the AIW SARP.
3
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 USN9796/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 Al G spent fuel modules shall not occur earlier that 270 days after shutdown.
(c)
Defueling grapple adaptors must be installed on all Al G spent fuel modules, and all modules must have control rods.
(U)
Control rod hold-down assemblies must be installed on applicable Al G spent fuel modules as identified in Section 1.2.5 of the Al G SARP, with the exception that control rod hold-down assemblies are not required for the Al G modules from the cored identified in Chapter Al of the A1G SARP Addendum.
(e)
The Al G core age and fuel type must be per Section 1.2.5 of the Al G SARP, with its addendum.
I (f)
The M-290 package loaded with Al G spent fuel modules must not be sealed for longer than 75 years.
C 8.
Failed fuel or fuel with defective cladding is not authorized for shipment.
C 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
/,
50 3
The A1G modules must be configured per Section 1.2.5 of the A1G SARP.
(g) The package must contain no more than 8.4 gallons of residual water.
Core Independent M-290 Safety Analysis Report for Packaging, dated May 13, 2013.
Supplements dated March 31, May20 and June 30, 2014; May 18, 2017; and May 9,2019.
FO THE U.S. NUCLEAR REGULATORY COMMISSION Jo McKirgan, Chief /
Snt Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear MatethSafety C
and Safeguards 00 4?
NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (6-2000) 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 USN9796/B(U)F-96 5
OF 5
REFERENCES Date: 7/c/J I
I I.-.
(I)
V.,,
Date Sign 3
, and February 8, 2024