ML23129A001

May 2, 2023, Summary of Meeting Duke Energy to Discuss an H. B. Robinson Steam Electric Plant, Unit No. 2 License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High

ML23129A001
Person / Time
Site:	Robinson
Issue date:	06/26/2023
From:	Michael Mahoney Plant Licensing Branch II
To:
Hood T
References
EPID L-2022-LLA-0137
Download: ML23129A001 (1)

Text

June 26, 2023 LICENSEE:

Duke Energy FACILITIES: H. B. Robinson Steam Electric Plant, Unit No. 2

SUMMARY

OF MAY 2, 2023, MEETING WITH DUKE ENERGY TO DISCUSS AN H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 LICENSE AMENDMENT REQUEST TO ADD FEEDWATER ISOLATION ON STEAM GENERATOR LEVEL HIGH-HIGH (EPID NO. L-2022-LLA-0137)

On May 2, 2023, a virtual observation public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Duke Energy (Duke, the licensee) to discuss the NRC staff's review of Duke's license amendment request (LAR) to add a new function to Technical Specifications 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation for Feedwater Isolation on Steam Generator Level High-High for the H. B. Robinson Steam Electric Plant, Unit No. 2 (Robinson). The meeting notice and agenda, dated April 13, 2023, are available in the Agencywide Documents Access and Management System (ADAMS) Accession No. ML23103A038. A list of attendees is provided in the enclosure.

The purpose of the meeting was to discuss the NRC staffs review of the licensees LAR dated September 21, 2022 (ML22264A149), as supplemented by .2|letter dated February 9, 2023]] (ML23040A426). The February 9 supplement was in response to an NRC staffs request for additional information (RAI) dated January 11, 2023 (ML23011A015).

Specifically, the purpose of this meeting was for NRC staff and the licensee to discuss an apparent discrepancy between the September 21, 2022, LAR and the licensees February 9, 2023, RAI response.

The staff discussed a discrepancy between a statement in the September 21, 2022, LAR on page 8 of 15 of the enclosure regarding how the Allowable Value (AV) for the Steam Generator Level High-High instrument channels were calculated (i.e., AV SP [setpoint] + GAFT [Group As-Found Tolerance]), versus how the value for AV was calculated in within the licensees February 9, 2023 supplemental response. Specifically, the AV was computed as AV SP +

GAFT on page 88 of 105 of Attachment 1 of the February 9, 2023, supplement within calculation RNP-I/INST-1070, Steam Generator Narrow Range Level Loop Uncertainty and Scaling Calculation.

The NRC staff provided information from Regulatory Issue Summary (RIS) 2006-17, NRC Staff Position on the Requirements of 10 CFR 50.36, Technical Specifications, Regarding Limiting Safety System Settings During Periodic Testing and Calibration of Instrument Channels, dated August 24, 2006. Specifically, NRC staff discussed requirements of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, with respect to limiting safety system settings (LSSSs) assessed during periodic testing and calibration of instrumentation and how LSSSs are related to AVs. NRC staff requested the licensee to verify and to change the equation of AV (AV SP + GAFT) in the document dated September 21, 2022, if appropriate by supplement to the LAR, because it did not appear to appropriately address the guidance in RIS 2006-17 for the increasing setpoint.

The licensee stated that they would supplement their LAR to provide clarity in statements made on page 8 of 18 of the enclosure of the LAR pertaining to the equation of the AV i.e., (AV = SP +

GAFT). The licensee stated that the supplement would provide an updated calculation (RNP-I/INST-1070, Steam Generator Narrow Range Level Loop Uncertainty and Scaling Calculation if any changes are required. The licensee stated they would provide a supplement by early June 2023.

There were no members of the public in attendance.

Please direct any inquiries to me at 301-415-3867, or Michael.Mahoney@nrc.gov.

Sincerely,

/RA/

Michael Mahoney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-261

Enclosure:

List of Attendees cc: Listserv

Enclosure LIST OF ATTENDEES MAY 2, 2023, PUBLIC MEETING WITH DUKE ENERGY H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 LICENSE AMENDMENT REQUEST TO ADD A NEW FUNCTION TO TECHNICAL SPECIFICATION 3.3.2 FOR FEEDWATER ISOLATION ON STEAM GENERATOR LEVEL HIGH-HIGH Name Organization Michael Mahoney U.S. Nuclear Regulatory Commission (NRC)

Hang Vu NRC Dave Rahn NRC Michael Waters NRC David Wrona NRC Calvin Cheung NRC Josh Duc Duke Energy (Duke)

Ryan Treadway Duke Jeff Abbott Duke Christy Ray Duke Samuel Shicks Duke Dustin Sims Duke Vijay Daji Duke Michael Blom Duke

Package: ML23129A002 Meeting Notice: ML23103A038 Meeting Summary: ML23129A001 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DORL/LPL2-2/BC NAME MMahoney RButler DWrona DATE 06/23/2023 05/11/2023 05/11/2023