ML23003A788
| ML23003A788 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 05/11/2023 |
| From: | Joel Wiebe Plant Licensing Branch III |
| To: | Rhoades D Constellation Energy Generation, Constellation Nuclear |
| Wiebe J | |
| References | |
| EPID L-2022-LLA-0131 | |
| Download: ML23003A788 (1) | |
Text
May 11, 2023 Mr. David P. Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer Constellation Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BYRON STATION, UNIT NO. 2 - REPORT FOR DECEMBER 12-16, 2022, REGULATORY AUDIT REGARDING REINSERTION OF A HIGH BURNUP ACCIDENT TOLERANT FUEL LEAD TEST ASSEMBLY (EPID L-2022-LLA-0131)
Dear Mr. Rhoades:
By letter dated August 31, 2022, Constellation Energy Generation, LLC (Constellation) submitted a license amendment request (LAR) for Byron Station, Unit No. 2 (Byron). In its LAR, Constellation proposes to revise language in Technical Specifications 2.1.1, Reactor Core SLs
[safety limits], and 4.2.1, Fuel Assemblies, to allow a previously irradiated accident tolerant fuel lead test assembly to be further irradiated during Byron Station, Unit No. 2, Cycle 25.
During the acceptance review of the LAR, the U.S. Nuclear Regulatory Commission (NRC) staff identified several items that required further clarification and additional detail. The NRC staff conducted a regulatory audit to support its review of the LAR in accordance with the audit plan.
dated November 17, 2022. A regulatory audit is a planned activity that includes the examination and evaluation of primarily non docketed information. The audit was conducted to increase the NRC staffs understanding of the LAR and identify information that will require docketing to support the NRC staffs regulatory finding. Enclosed for your information is a copy of the audit report.
Please contact me at 301-415-6606 or via e-mail at Joel.Wiebe@nrc.gov with any questions you may have regarding this letter.
Sincerely,
/RA/
Joel Wiebe, Senior Project Manager Licensing Projects Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. STN 50-455
Enclosure:
Audit Report
Enclosure REGULATORY AUDIT REPORT FOR BYRON, UNIT NO. 2, REGULATORY AUDIT REGARDING REINSERTION OF A HIGH BURNUP ACCIDENT TOLERANT FUEL LEAD TEST ASSEMBLY (EPID L-2022-LLA-0131)
1.0 BACKGROUND
By letter dated August 31, 2022 (Agencywide Documents Access and Management System Accession No. ML22243A094), Constellation Energy Generation, LLC (Constellation) submitted a license amendment request (LAR) for Byron Station, Unit No. 2 (Byron). In its LAR, Constellation proposes to revise language in Technical Specifications 2.1.1, Reactor Core SLs
[safety limits], and 4.2.1, Fuel Assemblies, to allow a previously irradiated accident tolerant fuel (ATF) lead test assembly (LTA) to be further irradiated during Byron Station, Unit No. 2, Cycle 25.
During the acceptance review of the LAR, the U.S. Nuclear Regulatory Commission (NRC) staff identified several items that required further clarification and additional detail. The NRC staff conducted a regulatory audit to support its review of the LAR in accordance with the audit plan.
dated November 17, 2022 (ML22304A680). A regulatory audit is a planned activity that includes the examination and evaluation of primarily non docketed information. The audit was conducted to increase the NRC staffs understanding of the LAR and identify information that will require docketing to support the NRC staffs regulatory finding.
2.0 REGULATORY AUDIT OBJECTIVES The objective of the audit was to increase review process efficiency through direct interaction with Constellation and Westinghouse technical experts. More specifically, the audits allowed the NRC staff to have extended discussions on the LAR, examine supportive documentation, and identify information that needs to be placed on the docket to complete the NRC staffs review.
The NRC, Constellation, and Westinghouse audit participants are provided below.
NRC Participants.
Santosh Bhatt John Lehning Joel Wiebe Constellation Participants Rebecca Steinman Bill Gassmann Phil Wengloski Chad Burns Westinghouse Participants Ernesto Pitruzzella Rachel Christian Michael Gavalek Kevin Barber Ann Marie DiLullo Radu Pomirleanu Peter Hilton Kurt Bevington 3.0 REGULATORY AUDIT BASES Regulatory guidance for the review of fuel system materials and designs and adherence to Title 10 of the Code of Federal Regulations, Appendix A to Part 50, General Design Criteria (GDC)-10, Reactor Design, is provided in NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (SRP), Section 4.4, Thermal and Hydraulic Design. In accordance with SRP, section 4.4, the objectives of the thermal and hydraulic designs safety review is to provide reasonable assurance that there should be a 95-percent probability at the 95-percent confidence level that a hot fuel rod in the reactor core will not experience a departure from nucleate boiling or a transition condition during normal operation or anticipated operational occurrences. As noted in the NRC staffs letter concerning the Clarification of Regulatory Path for Lead Test Assemblies, dated June 24, 2019, the evaluation of LTAs may necessitate the use of modified or different codes and methods than those currently approved. The letter further emphasizes the expectation that uncertainties in inputs and models conservatively use available data to the extent practical. Since a lead test assembly is under review evaluation of the LTAs may be made using sound engineering judgment and analytical codes and methods that reflect well-established engineering practices, and by conservatively addressing uncertainties in input parameters and models using the current state of knowledge and all available data to the extent practical.
4.0 DISCUSSION The NRC conducted an audit using audio/video conferencing via TEAMS and reviewed documents via an electronic portal. Any information exchanged that the NRC staff believed is necessary to achieve their regulatory conclusion will be formally requested in a request for additional information.
5.0 CONCLUSION
The audit accomplished the objectives listed in section 2.0 by allowing direct interaction with Westinghouse technical experts. The NRC staff participants were able to obtain clarification on multiple questions and examine calculation notes and supporting documentation. The NRC staff will issue RAIs on the open items discussed at the audit exit where information is needed on the docket to support the NRC staffs safety evaluation.
ML23003A788 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DSS/SNSB/BC(A)
NAME JWiebe SRohrer DWoodyatt DATE 01/03/23 1/4/23 1/30/23 OFFICE NRR/DORL/LPL3/BC(A)
NRR/DORL/PL3/PM NAME VSreenivas JWiebe DATE 4/25/23 5/11/23