ML23129A001

From kanterella
Jump to navigation Jump to search

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 Duke Energy icon.png
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

SUBJECT:

SUMMARY

OF MAY 2, 2023, M EETING 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 res ponse 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 st atement 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 calibr ation 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

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

Enclosure

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