ML24214A156
| ML24214A156 | |
| Person / Time | |
|---|---|
| Site: | 99900003 |
| Issue date: | 08/02/2024 |
| From: | Glisan J NRC/NRR/DNRL/NLIB |
| To: | Hayes M NRC/NRR/DNRL |
| References | |
| Download: ML24214A156 (1) | |
Text
August 2, 2024 MEMORANDUM TO:
Michelle W. Hayes, Chief Licensing and Regulatory Infrastructure Branch Division of New and Renewed Licenses Office of Nuclear Reactor Regulation FROM:
Jordan D. Glisan, Project Manager /RA/
Licensing and Regulatory Infrastructure Branch Division of New and Renewed Licenses Office of Nuclear Reactor Regulation
SUBJECT:
U.S. NUCLEAR REGULATORY COMMISSION
SUMMARY
OF THE JUNE 12, 2024, PUBLIC MEETING WITH GE-HITACHI NUCLEAR ENERGY AMERICAS, LLC TO DISCUSS CLARIFICATION OF NRC STAFF DRAFT LIMITATIONS AND CONDITIONS On August 9, 2023, the U.S. Nuclear Regulatory Commission (NRC) accepted GE-Hitachi Nuclear Americas, LLC (GEH) licensing topical report (LTR) NEDC-33926P/NEDO-33926,BWRX-300 Steel-Plate Composite Containment Vessel and Reactor Building Structural Design. The NRC staff is currently reviewing the LTR and will issue a final safety evaluation to the public once complete.
The NRC held a virtual observation public meeting on June 12, 2024, with GE-Hitachi Nuclear Energy Americas, LLC (GEH), to discuss NRC staff draft limitations and conditions developed during its review of the GEH BWRX-300 Steel-Plate Composite Containment Vessel and Reactor Building Structural Design topical report. Specifically, GEH requested the meeting to gain clarification on the select limitations and conditions found at Agencywide Documents and Access Management System (ADAMS) Accession No. ML24164A141. These draft limitations and conditions were made publicly available to support this public meeting and were attached the meeting notice. Subsequent to the public meeting, the NRC staff issued its draft safety evaluation report and can be found at ML24178A426.
CONTACT: Jordan Glisan, NRR/DNRL 301-415-3478
M. Hayes 2
Preapplication engagements, including this meeting, provide an opportunity for the NRC staff to engage in early discussions with a prospective applicant to offer licensing guidance and to identify potential licensing issues early in the licensing process. No decisions or commitments were made during the preapplication meeting.
The NRC issued the public meeting notice (ML24164A162) and posted it on the NRC public website. The agenda is included in the public meeting notice.
Enclosed are the list of participants for the meeting (Enclosure 1) and a summary of the meeting (Enclosure 2).
Docket No. 99900003
Enclosures:
- 1. List of Attendees
- 2. Summary of Meeting cc w/enclosure: GEH BWRX-300 Gov Delivery
- via email NRR-106
U.S. NUCLEAR REGULATORY COMMISSION
SUMMARY
OF THE JUNE 12, 2024, PUBLIC MEETING WITH GE-HITACHI NUCLEAR ENERGY AMERICAS, LLC TO DISCUSS CLARIFICATION OF NRC STAFF DRAFT LIMITATIONS AND CONDITIONS Meeting Attendees Name Organization Jordan Glisan NRC Ian Tseng NRC George Thomas NRC Michelle Hayes NRC Jim Shea NRC George Stoyanov CNSC Lamia Chouha GEH Cybil Miller GEH Luis Hinojosa GEH Martin Flynn GEH Peter Ostrowski GEH Ahmed Ashour GEH Osama Bedair GEH Ossama Ali GEH Mohtady Sherif GEH Sukjoon Kim Argonne National Labs Addison Hall Dominion Energy Michele Moorrees Tennessee Valley Authority Andrew Dewhurst Tennessee Valley Authority
U.S. NUCLEAR REGULATORY COMMISSION
SUMMARY
OF THE JUNE 12, 2024, PUBLIC MEETING WITH GE-HITACHI NUCLEAR ENERGY AMERICAS, LLC TO DISCUSS CLARIFICATION OF NRC STAFF DRAFT LIMITATIONS AND CONDITIONS Meeting Summary The U.S. Nuclear Regulatory Commission (NRC) held a virtual observation public meeting on June 12, 2024, with GE-Hitachi Nuclear Energy Americas, LLC (GEH), to discuss NRC staff draft limitations and conditions developed during its review of the GEH BWRX-300 Steel-Plate Composite Containment Vessel (SCCV) and Reactor Building (RB) Structural Design topical report (TR). Specifically, GEH requested the meeting to gain clarification on the select limitations and conditions found at Agencywide Documents and Access Management System (ADAMS) Accession No. ML24164A141.
GEH started the discussion by sharing the limitations and conditions they requested clarification for and highlighted the areas for clarification.
In limitation and condition 8.1 (f), GEH sought clarification on the wording in the second statement. As a result of this meeting, the NRC staff agreed to remove the second statement of this limitation and condition. The second statement was found to be duplicative of the first statement since the configurations in TR Section 3.4 are considered to be bounded by the NRIC testing described in Section 7.0.
Regarding limitation and condition 8.1 (j), GEH asked for clarification on the NRC staff position that ANSI/AISC N690-18, Appendix N4 addresses only life safety for evacuation in the event of a fire but does not address either important to Safety structural steel members or loading condition associated with a facility fire. The NRC staff agreed to clarify this item by specifically citing that meeting the fire protection requirements of GDC 3 and 10 CFR 50.48 is outside the scope of the TR.
Lastly, in limitation and condition 8.11, GEH wanted clarification on why the NRC staff is requiring GEH to provide further evaluation of any residual stresses and strains resulting from rolling of the curved plates because the faceplates will be fabricated per CC-4000 provisions of American Society of Mechanical EngineersSection III, Division 2 for SCCV and ANSI/AISC N690-18 for the RB. The NRC staff held that the N690 standard does not address curved elements and the effects of curvature on detailing and design needs to be evaluated. Further, the fabrication provisions of CC-4000 for SCCV are for traditional concrete containment liners for which radius of curvature-to-liner thickness ratio significantly over 20 such that the effects of residual stresses and strains from rolling may be negligible. However, the TR allows for use of lower radius of curvature to wall-panel thickness ratio as low as 2.0, and therefore the potential effects of residual stresses and strains from rolling may be more significant and will need to be evaluated and addressed in the detailed design. The NRC staff stated that this isnt adequately addressed in the TR and therefore, requires more evaluation in a license application where the methodology is to be incorporated. This condition did not change as a result of this clarification call.
2 The meeting adjourned at 1:37 pm.