ML18296A056
| ML18296A056 | |
| Person / Time | |
|---|---|
| Site: | 07109297 |
| Issue date: | 10/23/2018 |
| From: | Pierre Saverot Spent Fuel Licensing Branch |
| To: | Stilwell W Westinghouse |
| Saverot P | |
| References | |
| EPID L-2018-LLA-0234 | |
| Download: ML18296A056 (4) | |
Text
T. Tate UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 23, 2018 Mr. Wes Stilwell Global Packaging and Regulatory Compliance Manager Westinghouse Electric Company LLC 5801 Bluff Road Hopkins, SC 29061
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE MODEL NO. TRAVELLER PACKAGE.
Dear Mr. Stilwell:
By letter dated September 4, 2018, you submitted an application for a special package authorization for the transport of two Accident Tolerant Fuel assemblies in the Model No.
Traveller package.
The staff has determined that further information is needed to complete its technical review.
The information requested is listed in the enclosure to this letter. We request that you provide this information by November 27, 2018.
Please reference Docket No. 71-9297 and EPID - L-2018-LLA-0234 in future correspondence related to this licensing action. If you have any questions regarding this matter, please contact me at 301-415-7505.
Sincerely,
/RA/
Pierre Saverot, Project Manager Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards Docket No. 71-9297 EPID - L-2018-LLA-0234
Enclosure:
Request for Additional Information
ML18296A056 OFFICE:
NMSS/DSFM NMSS/DSFM NMSS/DSFM NMSS/DSFM NMSS/DSFM NAME:
PSaverot RTorres DTang MRahimi DATE:
10/10/2018 10/11/2018 10/16/2018 10/12/2018 OFFICE:
NMSS/DSFM NMSS/DSFM NMSS/DSFM NAME:
YDiaz-Sanabria SFigueroa JMcKirgan DATE:
10/19/2018 10/18/2018 10/23/2018
Enclosure Request for Additional Information Westinghouse Electric Company LLC Docket No. 71-9297 Model No. TRAVELLER Package By letter dated September 4, 2018, Westinghouse Electric Company, LLC, submitted an application for a special package authorization for the transport of two accident tolerant fuel (ATF) fuel assemblies in the Model No. Traveller package.
The two types of ATF designs included in this request are U3Si2 pellets and Advanced Doped Pellet Technology (ADOPT) pellets. The ATF pellet types are stacked in separate lead test rods (LTRs) on the periphery of an assembly and arranged in separate lead test assemblies (LTA).
For this special authorization request, LTA1 includes only U3Si2 rods and LTA2 includes only ADOPT rods. Additionally, some periphery rods in both LTAs have a chromium coating on the rod cladding. There is no change to the Traveller packaging design.
This request for additional information (RAI) identifies information needed by the U.S. Nuclear Regulatory Commission (NRC) staff (the staff) in connection with its review of the application.
Each individual RAI describes information needed by the staff to complete its review of the application and to determine whether the applicant has demonstrated compliance with the regulatory requirements of Title 10 of the Code of Federal Regulations (10 CFR) Part 71.
Chapter 2 STRUCTURAL AND MATERIALS REVIEW:
2-1 Justify the conclusion that the chromium coating does not affect the melt temperature or thermal performance of the base cladding alloy, and that the fuel pellet and cladding thermal properties in Table 3-3A of the application remain valid for the transport of the ATF LTAs.
The applicant concluded that the material thermal properties reviewed by the NRC staff in support of the currently approved CoC, Revision 10, are valid for the packages thermal evaluation for ATF LTA contents, since the chromium coating of the ATF LTA fuel rod cladding does not affect the melt temperature or thermal performance of the base alloy.
The applicant did not provide any evidence in support of this conclusion, e.g., a justification of whether any credible eutectic products can lower the melting point of the base cladding.
Further, the applicant has not justified the validity of the thermal material properties in Table 3-3A of the application for the evaluation of tests per 10 CFR 71.71 and 71.73 per the revised pellet composition.
The information is needed to ensure compliance with 10 CFR 71.71(c)(1) and 71.73(c)(4).
2-2 Evaluate the potential for the 13.183-inch long U3Si2 rods to experience any lattice expansion associated with the fuel rod post-buckling bending deformation, in view of the fuel geometry change resulting from the CTU 9-m drop tests per Tables 2-47 through 2-50 of the application. Provide design drawing(s) to delineate the axial location(s) of the U3Si2 rods to show that the U3Si2 rods are placed outside of the region susceptible of bending deformations.
Figure 2-117, Traveller Prototype Interior after Test 1.2, indicates that the lateral deformation of a few rods is likely to be limited to the bottom portion of a fuel assembly subject to a 9-m end drop test. Thus, staff needs to verify that, because of their placement location, the U3Si2 rods are unlikely to be subject to large bending deformations and will maintain an adequate structural performance.
The information is needed to ensure compliance with 10 CFR 71.73(c)(1).
2-3 Provide an evaluation of the structural capabilities of the U3Si2 rod.
The evaluation, to be performed using the information from the design drawing(s), needs to show that the axial strength of the joints and the flexural rigidity of the U3Si2 rod assembly are at least equivalent to those for the balance of the fuel rods undergoing the 9-m drop tests.
This information is needed to ensure compliance with 10 CFR 71.73(c)(1).