ML21183A062
| ML21183A062 | |
| Person / Time | |
|---|---|
| Site: | 07109380 |
| Issue date: | 07/12/2021 |
| From: | Pierre Saverot Storage and Transportation Licensing Branch |
| To: | Christopher Regan Division of Fuel Management |
| PSaverot NMSS/DFM/STL 301.415.7505 | |
| Shared Package | |
| ML21183A061 | List: |
| References | |
| EPID L-2021-LLA-0102 | |
| Download: ML21183A062 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 12, 2021 MEMORANDUM TO: Christopher M. Regan, Deputy Director Division of Fuel Management Office of Nuclear Material Safety and Safeguards Signed by Saverot, Pierre FROM: Pierre Saverot, Project Manager on 07/12/21 Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards
SUBJECT:
SUMMARY
OF JUNE 24, 2021 MEETING WITH WESTINGHOUSE ELECTRIC COMPANY LLC
Background
On June 24, 2021, an Observation Public Meeting was held by teleconference between the NRC staff and representatives from Westinghouse Electric Company LLC (Westinghouse) to discuss a pending amendment request for the Model No. Traveler STD and XL packages. This pre-application meeting was noticed on June 4, 2021 (ADAMS Accession No. ML21155A009).
The meeting attendance list and the presentation are provided as Enclosure Nos. 1 and 2, respectively.
Discussion Westinghouse is planning to submit an amendment request for its Model No. Traveler STD and XL packages (Docket No. 71-9380) by mid-July 2021. The amendment request will include a new bottom support spacer for a new fuel assembly 4-legged skirted bottom nozzle design, a new chromium-coated cladding and optimized-ZIRLO liners (OZL), an aluminum and stainless-steel cladding for the loose rods, ADOPT UO2 fuel, 7% enrichment loose fuel rods and 6%
enrichment fuel assembly as authorized contents.
Regarding the new bottom support spacer, Westinghouse benchmarked the current design drop test, determined the impact force applied to the fuel assembly, and compared the impact limiter crush depth to the physical test. Westinghouse then re-run the finite element analysis with the new support spacer design and compared the impact limiter crush distance to the benchmarked analysis and physical tests.
CONTACT: Pierre Saverot, NMSS/DFM 301-415-7505
C. Regan Regarding the new cladding material, Westinghouse explained that the A2T1-H cladding is an aluminum-magnesium-chromium alloy that is 96.7% weight percent aluminum, while the stainless-steel cladding is an annealed Type 304 stainless steel. Westinghouse said that the structural properties, total strain energy absorption, and melt temperatures of the new cladding materials were compared to, and are bounded by, the package HAC tested Zircaloy cladding and that the maximum temperature of the fuel cladding is the 104°C temperature inside the clam shell, as observed during hypothetical accident conditions. Westinghouse explained that the low tin in the OZL zirconium-tin-iron alloy liner provides corrosion resistance and lower growth in the rod assembly. Westinghouse also explained the various chromium coating methods, i.e., cold spray polishing process and pressure vapor deposition (PVD) and said that autoclave tests were done for both methods.
In response to a staffs question, Westinghouse confirmed that about 20 additional benchmark experiments were added for enrichments above 5%. Staff asked Westinghouse to clarify why it appeared that the expanded pitch modeling under HAC had been apparently removed from the model in order to reduce k-eff. Similarly, staff noted that the applicant also removed conservatisms in the polyethylene modeling in order to reduce k-eff, and asked Westinghouse to identify in the application a technical basis for doing so. Finally, staff asked if the applicant did any sensitivity/uncertainty (i.e., TSUNAMI) calculations to determine the applicability of experiments currently in the suite, as well as of the newly added higher enriched experiments, to the 6% and 7% enriched contents, and Westinghouse confirmed there was no such calculation made.
A shipment from the United Kingdom (U.K.) to a U.S. reactor is scheduled in early 2023. Due to the time required by the U.K Regulatory Authorities to revalidate the NRC certificate, Westinghouse will need the revised CoC by January 2022.
No regulatory commitments were made during this meeting.
Docket No. 71-9380 EPID L-2021-LLA-0102
Enclosures:
1- Meeting Attendees 2- Presentation
C. Regan Meeting Between Westinghouse Electric Company LLC and the Nuclear Regulatory Commission June 24, 2021 Meeting Attendees NRC/NMSS/DFM Pierre Saverot Patrick Koch Jeremy Smith Andrew Barto Darrell Dunn Chris Sydnor WESTINGHOUSE Tanya Sloma-DeLosier Wes Stilwell Brian Millare Charlie Murphy (Daher-TLI)
Hawk Rochow (NovaTech)
Enclosure 1
ML21183A061; Memo ML21183A062 OFFICE NMSS/DFM/STLB NMSS/DFM/STLB NMSS/DFM/STLB NMSS/DFM/STLB NAME PSaverot PS PSaverot PS JMcKirgan JM SFigueroa SF DATE Jul 5, 2021 Jul 6, 2021 Jul 7, 2021 Jul 12, 2021 OFFICE NMSS/DFM/STLB NAME PSaverot PS DATE Jul 12, 2021