ML21102A061
| ML21102A061 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/27/2021 |
| From: | Stone Z, Shawn Williams Plant Licensing Branch II |
| To: | Burchfield J Duke Energy Carolinas |
| Zachery Stone-NRR/DORL 301-415-0615 | |
| Shared Package | |
| ML21102A059 | List: |
| References | |
| EPID L-2021-LRM-0033 | |
| Download: ML21102A061 (4) | |
Text
April 27, 2021 LICENSEE: Duke Energy Carolinas, LLC FACILITY: Oconee Nuclear Station, Units 1, 2, and 3
SUBJECT:
SUMMARY
OF APRIL 14, 2021, PUBLIC MEETING WITH DUKE ENERGY CAROLINAS, LLC, REGARDING PRE-APPLICATION MEETING TO DISCUSS PROPOSED RELIEF REQUEST RELATED TO CODE CASE N-853 (EPID L-2021-LRM-0034)
On April 14, 2021, an Observation public meeting (teleconference), formally known as a Category 1 public meeting, was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Duke Energy Carolinas, LLC (Duke Energy, the licensee). The purpose of the meeting was for Duke Energy to discuss a proposed relief request to use American Society of Mechanical Engineers (ASME) Code,Section XI, IWB-3514 acceptance criteria in lieu of the NB-5330 acceptance criteria with regards to Code Case N-853 for reactor coolant system nozzle welds for Oconee Nuclear Station, Units 1, 2, and 3 (Oconee).
The meeting notice and agenda, dated March 15, 2021, are available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML21078A098. A list of attendees is provided as an Enclosure. The licensees presentation is available in ADAMS at Accession No. ML21102A063.
Background
On February 26, 2020, the NRC authorized the use of Relief Request 19-ON-001 at Oconee for the remainder of the fifth 10-year inservice inspection (ISI) intervals (ADAMS Accession No. ML20055F571). This allowed the use of ASME Code Case N-853 to repair or proactively mitigate Alloy 600 nozzle welds with two deviations.
Teleconference During the teleconference, Duke Energy discussed its lessons learned from the Oconee Unit 1 refueling outage, where the licensee utilized Code Case N-853 for Alloy 600 nozzle weld repairs. The licensee suggested using ASME Section XI, IWB-3514 acceptance criteria in lieu of NB-5330 would avoid potential outage re-work that provides no safety or quality benefit.
NRC Questions to Duke Energy The NRC staff asked which thickness would be used for the flaw evaluations as per ASME Code Section XI, IWB-3514 (i.e., thickness of the weld overlay or the thickness of the overlay and pipe wall). The licensee stated that the overlay thickness would be used. The licensee clarified that this acceptance criteria change is just for the weld pad itself. The NRC staff asked what the difference is between the approved Code Case N-853 relief request and this proposal,
and if the repair method will be the same. The licensee stated that the acceptance criteria is the only change and the repair method is still the same. The NRC staff noted that the most recent precedent discussed was for Oconee in 2007, and the NRC staff asked if there was any other precedence or if this is unique to Oconee? The licensee stated that the reason for this being applicable to Oconee is due to its use of the Code Case N-853 to perform Alloy 600 nozzle weld repairs. The licensee was unsure regarding other precedence in using this acceptance criteria for the weld pads. The NRC staff questioned the licensees proposed submittal and needed approval date. The NRC staff also questioned if this would only be beneficial for Units 2 and 3.
The licensee stated that its submittal would seek NRC approval by the Unit 2 fall outage of 2021. The licensee stated that, if this proposal is not approved by this timeline, then the proposed relief request would have to be reassessed for its benefit as it is only applicable for Units 2 and 3 since the Unit 1 nozzle work was completed in the 2020 refueling outage with the current Code Case N-853 acceptance criteria. The NRC staff asked if rework was identified during the Unit 1 refueling outage during Alloy 600 nozzle weld repairs using the Code Case N-853. The licensee stated that there was no rework required on any of the Alloy 600 nozzle weld repairs during the Unit 1 refueling outage, but this issue was identified during the mockup and training phase before the Unit 1 refueling outage.
Public Questions to NRC No members of the public were in attendance.
Closing No regulatory decisions or commitments were made during the meeting. Public Meeting Feedback forms were available, but no comments were received.
Please direct any inquiries to me at 301-415-1009, or shawn.williams@nrc.gov.
/RA/
Shawn Williams, Senior Project Manager Plant Licensing Branch, II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, 50-287
Enclosures:
List of Attendees cc: Listserv
LIST OF ATTENDEES APRIL 14, 2021, PUBLIC MEETING WITH DUKE ENERGY CAROLINAS REGARDING A PRE-APPLICATION MEETING TO DISCUSS PROPOSED RELIEF REQUEST RELATED TO CODE CASE N-853 OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 Nuclear Regulatory Commission Staff Zackary Stone Shawn Williams Ali Rezai Stephen Cumblidge Jared Nadel John Lamb Duke Energy Carolinas Participants Arthur Zaremba Josh Duc Jim Axline David Peltola Chris Lohse Stephen Roe Enclosure
Meeting Notice ML21078A098 Meeting Summary ML21102A061 Handouts ML21102A063 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA DNRL/NPHP/BC NAME ZStone SWilliams KGoldstein MMitchell DATE 4/15/2021 4/16/2021 04/26/2021 4/20/21 OFFICE NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME MMarkley SWilliams DATE 4/27/2021 4/27/2021