ML24340A064
| ML24340A064 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/06/2024 |
| From: | Samson Lee Plant Licensing Branch IV |
| To: | Wolf Creek |
| Lee S, 301-415-3168 | |
| References | |
| EPID L-2024-LRM-0136 | |
| Download: ML24340A064 (1) | |
Text
December 6, 2024 LICENSEE:
Wolf Creek Nuclear Operating Corporation FACILITY:
Wolf Creek Generating Station, Unit 1
SUBJECT:
SUMMARY
OF DECEMBER 3, 2024, PRESUBMITTAL TELECONFERENCE WITH WOLF CREEK NUCLEAR OPERATING CORPORATION REGARDING A LICENSE AMENDMENT REQUEST TO ADOPT 10 CFR 50.69, RISK-INFORMED CATEGORIZATION AND TREATMENT OF STRUCTURES, SYSTEMS AND COMPONENTS FOR NUCLEAR POWER REACTORS, FOR WOLF CREEK GENERATING STATION, UNIT 1 (EPID L-2024-LRM-0136)
On December 3, 2024, an Observation public teleconference was held between the U.S.
Nuclear Regulatory Commission (NRC) and representatives of the Wolf Creek Nuclear Operating Corporation (the licensee). The purpose of the presubmittal teleconference was to discuss preliminary information regarding the licensees planned submission of a license amendment request (LAR) for Wolf Creek Generating Station, Unit 1 (Wolf Creek), to add a new license condition to allow for the implementation of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.69, Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors. Section 50.69 of 10 CFR allows adjustment of the scope of structures, systems, and components (SSCs) subject to special treatment requirements (e.g., quality assurance, testing, inspection, condition monitoring, assessment, and evaluation) based on an integrated, systematic, risk-informed process for categorizing SSCs according to their safety significance. The licensees presentation slides are available in Agencywide Documents Access and Management System (ADAMS) Accession No. ML24311A157. The meeting notice and agenda dated November 13, 2024, are available in ADAMS at Accession No. ML24318C463. A list of attendees is enclosed.
During the meeting, the licensee indicated that the proposed 10 CFR 50.69 LAR would be based on Nuclear Energy Institute (NEI) 00-04, 10 CFR 50.69 SSC Categorization Guideline, except for seismic and high winds. There were no open facts and observations for the Wolf Creek internal events, flooding, and fire probabilistic risk assessment models. All external hazards were screened. The licensee planned to propose an alternative approach for seismic risk categorization using the same process licensed for LaSalle County Station (LaSalle). A high winds fragility analysis was performed, and the licensee planned to propose an alternative bounding approach for assessing high winds risk. The licensee also planned to propose a 60-day implementation period.
In response to NRC staff questions, the licensee indicated that they continued to consider a range of implementation periods based on industry experience. The licensee also indicated that its approach to assess seismic risk would follow the same approach licensed for LaSalle and other Electric Power Research Institute Tier 2 plants.
The licensee indicated that it planned to submit the 10 CFR 50.69 LAR in December 2024.
However, the licensee considered that its forthcoming LAR to adopt Technical Specifications Task Force (TSTF) Traveler TSTF-505, Provide Risk-Informed Extended Completion Times -
RITSTF [Risk-Informed TSTF] Initiative 4b to have a higher priority.
Two members of the public were in attendance. The public did not provide any comments.
No regulatory decisions were made at this meeting.
Please direct any inquiries to me at 301-415-3168 or by email at Samson.Lee@nrc.gov.
/RA/
Samson S. Lee, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosure:
List of Attendees cc: Listserv
Enclosure LIST OF ATTENDEES DECEMBER 3, 2024, PRESUBMITTAL TELECONFERENCE REGARDING LICENSE AMENDMENT REQUEST TO ADOPT 10 CFR 50.69, RISK-INFORMED CATEGORIZATION AND TREATMENT OF STRUCTURES, SYSTEMS AND COMPONENTS FOR NUCLEAR POWER REACTORS WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION, UNIT 1 U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation Samson Lee - DORL,1 LPL42 Hannah McLatchie - DORL, LPL4 Robert Pascarelli - Branch Chief, DRA,3 APLA4 Malcolm Patterson - DRA, APLA April Pulvirenti - DRA, APLA Jay Robinson - DRA, APLB5 Alissa Neuhausen - Branch Chief, DRA, APLC6 Stephanie Garza - DRA, APLC Daniel Silverstein - DRA, APLC Fred Forsaty - DSS,7 SNSB8 Catie Szumski - DSS, SNSB Gokul Vasudevamurthy - DSS, SNSB Wolf Creek Nuclear Operating Corporation Dustin Hamman - Director of Nuclear and Regulatory Affairs Jeff Suter - Engineering Manager and PRA (Presenter)
Josh Turner - Manager of Regulatory Affairs Grant Bussard - Manager Engineering David Alford - PRA Mark Barraclough - 50.69 Program Engineer Don Garbe - Fire Protection Nathan Lee - Licensing Lu Huang - PRA Paul Nguyen - PRA 1 Division of Operating Reactor Licensing 2 Plant Licensing Branch IV 3 Division of Risk Assessment 4 Probabilistic Risk Assessment (PRA) Licensing Branch A 5 PRA Licensing Branch B 6 PRA Licensing Branch C 7 Division of Safety Systems 8 Nuclear Systems Performance Branch Contractors to Wolf Creek Nuclear Operating Corporation Amanda Gaines - Framatome Rick Grantom - Framatome Ralph Chackal - Framatome Jim Moody - Framatome Justin Wheat - Framatome Public Carroll Trull - EPM Aram Kayserian - EPM
ML24340A183 (Package)
ML24318C463 (Meeting Notice)
ML24311A157 (Meeting Slides)
ML24340A064 (Meeting Summary)
- concurrence by email NRC-001 OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA* NRR/DORL/LPL4/BC* NRR/DORL/LPL4/PM*
NAME SLee PBlechman TNakanishi SLee DATE 12/5/2024 12/5/2024 12/06/2024 12/06/2024