ML21063A328

Public Mtg Summary March 4, 2021 with Southern Nuclear Operating Company, Inc., a Proposed LAR to Change the TS Related to Heat Flux Hot Channel Factor for Joseph M. Farley Nuclear Plant, Units 1 & 2, and Vogtle Electric Generating Plant, U

ML21063A328
Person / Time
Site:	Vogtle, Farley
Issue date:	03/12/2021
From:	John Lamb NRC/NRR/DORL/LPL2-1
To:	Southern Nuclear Operating Co
J G Lamb NRR/DORL
Shared Package
ML21063A327	List: ML21063A328
References
(EPID No. L 2021 LRM 0023) TS 3.2.1
Download: ML21063A328 (6)

Text

March 12, 2021 LICENSEE: Southern Nuclear Operating Company, Inc.

FACILITY: Joseph M. Farley Nuclear Plant, Units 1 and 2, and Vogtle Electric Generating Plant, Units 1 and 2

SUMMARY

OF MARCH 4, 2021, PUBLIC MEETING WITH SOUTHERN NUCLEAR OPERATING COMPANY, INC., REGARDING A PROPOSED LICENSE AMENDMENT REQUEST TO CHANGE THE TECHNICAL SPECIFICATION RELATED TO HEAT FLUX HOT CHANNEL FACTOR FOR JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2, AND VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 (EPID NO. L-2021-LRM-0023)

On March 4, 2021, an Observation public meeting formally known as a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Southern Nuclear Operating Company, Inc. (SNC, the licensee). The purpose of the meeting was for SNC to describe its plan to submit a license amendment request (LAR) to change the Technical Specification (TS) related to the heat flux hot channel factor for Joseph M. Farley Nuclear Plant, Units 1 and 2; and Vogtle Electric Generating Plant, Units 1 and 2 (Farley and Vogtle). SNC proposed to submit a LAR to revise TS 3.2.1, Heat Flux Hot Channel Factor (FQ(Z)) (FQ Methodology).

SNC proposed to revise Farley and Vogtles TS requirements regarding heat flux hot channel factor, in accordance with the Westinghouse Topical Report WCAP-17661-P-A, Revision 1, Improved RAOC [Relaxed Axial Offset Control] and CAOC [Constant Axial Offset Control]

FQ Surveillance Technical Specifications (Agencywide Document and Access Management System (ADAMS) Accession No. ML19225C138). In addition, the licensee proposed to implement Technical Specification Task Force (TSTF)-99 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML040480063), TSTF-241 (ADAMS Accession No. ML040611034), and TSTF-290 (ADAMS Accession No. ML040630063). TSTF-99 would extend the Completion Time for FQ(w) not within limits from two hours to four hours. TSTF-241 would allow time for stabilization after reducing power due to Quadrant Power Tilt Ration (QPTR) out of limit. TSTF-290 would provide revisions to hot channel factor specifications.

A list of attendees is provided as an Enclosure.

On February 18, 2021 (ADAMS Accession No. ML21049A258), the meeting was noticed on the NRC public webpage.

The SNC presented slides contained in ADAMS Accession No. ML21057A018.

Introduction The NRC staff opened the meeting with introductory remarks and introduction of the attendees.

The SNC staff discussed the following topics: (1) background information, and (2) the proposed LAR.

Background

On February 28, 1994 (ADAMS Accession No. ML080630389 - this is non-public because it contains proprietary information), the safety evaluation related to the Westinghouse Electric Company (Westinghouse) Topical Report (TR), titled WCAP-10216-P-A, Rev 1A, Relaxation of Constant Axial Offset Control (and) FQ Surveillance Technical Specification, was issued.

SNC stated that Westinghouse identified a non-conservatism associated with TS 3.2.1, Required Action B, in February 2009.

Westinghouse issued a Nuclear Safety Advisory Letter (NSAL) NSAL-09-5, Revision 1, Relaxed Axial Offset Control FQ Technical Specification Actions, dated September 23, 2009.

Westinghouse issues NSALs to its customers to communicate a potential safety issue so that the customers can conduct a review of the issue and determine whether any action is required.

The NRC does not have an official record copy of NSAL-09-05.

By letter dated January 2, 2014 (ADAMS Accession No. ML14009A092), the Pressurized-Water Reactor Owners Group (PWROG) submitted TR WCAP-17661-P, Revision 1, in order to develop a solution to the problem identified in NSAL 09-05.

SNC stated that Farley and Vogtle identified a non-conservatism associated with TS 3.2.1, SR 3.2.1.2.

On February 3, 2015, Westinghouse issued NSAL-15-1, Heat Flux Hot Channel Factor Technical Specification Surveillance, after determining that one aspect of TS SR 3.2.1.2 may not be sufficient to assure that the peaking factor that is assumed in the licensing basis analysis is maintained under all conditions between the frequency of performance of TS SR 3.2.1.2.

Westinghouse issues NSALs to its customers to communicate a potential safety issue so that the customers can conduct a review of the issue and determine whether any action is required.

The NRC does not have an official record copy of NSAL-15-1.

SNC said that NSAL-15-1 guidance is no longer required once the WCAP-17661-P based TSs are implemented.

By letter dated November 23, 2018 (ADAMS Accession No. ML18298A314 - not available to the public), the NRC issued a proprietary version safety evaluation (SE) for WCAP-17661, Revision 1.

By letter dated August 23, 2019 (ADAMS Accession No. ML19225D179), the NRC issued verification letter noting WCAP-17661-NP is acceptable for referencing in licensing applications with limitations.

SNC stated that NSAL-09-5 was entered in the Corrective Action Program (CAP) for Farley and Vogtle. The licensee also said that NSAL-15-1 was entered in the CAP. SNC explained that

the corrective actions remain open pending approval of the proposed LAR. The licensee said that SNC will request the adoption of WCAP-17661-P-A with limitations specified in the NRC SE dated November 23, 2018. In addition, SNC will request the adoption of three TSTFs: (1)

TSTF-99-A, (2) TSTF-241-A, and (3) TSTF-290-A. The licensee stated that TSTF-99-A is to extend Limited Condition of Operation (LCO) 3.2.1B, Required Action B.1 Completion Time from two hours to four hours. SNC said that TSTF-241-A is to allow time for stabilization after reducing power due to QPTR out of limit. The licensee stated that TSTF-290-A is to revise the hot channel factor specifications.

Proposed LAR SNC stated that it plans to resolve the non-conservative TS issues identified in NSAL-09-05, Revision 1, and NSAL-15-1 by submitting a proposed LAR for Farley and Vogtle. The licensee said that the proposed LAR will change TS 3.2.1 for Farley and Vogtle. SNC plans to change TS 3.2.1 to implement surveillance formulations and required actions as shown in WCAP-17661-P-A, Revision 1. The licensee said it plans to apply approval limitations in the associated NRC SE for WCAP-17661-P-A, Revision 1. SNC stated that the first limitation is the use of AXY and AQ, and the second limitation is the power level reduction to 50-percent of rated thermal power (RTP). The licensee also said it plans to implement TSTF-99-A, TSTF-241-A, and TSTF-290-A, in the same proposed LAR with the implementation of WCAP-17661-P-A, Revision 1.

SNC stated that the proposed LAR will change the following: (1) TS 3.2.1, Condition A, (2) TS 3.2.1, Condition B, (3) Surveillance Requirement (SR) 3.2.1.1, (4) SR 3.2.1.2, and (5) TS 5.6.5, Core Operating Limits Report (COLR).

SNC said that it plans to submit the proposed LAR in March 2021, and SNC will request approval by March 2022. The licensee stated that it plans to implement the proposed LAR after the next refueling outage for each unit.

NRC Questions to SNC The NRC staff asked what actions SNC took after receiving the NSALs for Farley and Vogtle.

The licensee said an entry was made into its CAP. The NRC staff questioned if SNC was going to meet the two limitations from WCAP-17661-P-A, Revision 1. SNC stated that it would fully comply with the limitations and it will be explained in the proposed LAR. The NRC staff asked if the proposed TSTF changes will have justifications in the proposed LAR. The licensee said that the proposed LAR will have justifications for each of the TSTF changes. The NRC staff questioned if it would be more efficient if the TSTFs were reviewed independently. SNC stated that WCAP changes are the essential changes for the non-conservative TS, and the TSTFs are making conforming changes to align with the WCAP. The licensee said there are precedents for implementing WCAP-17661-P-A, and the NRC approved similar changes for Prairie Island and Watts Bar.

Public Questions to NRC There were no members of the public in attendance.

Closing The NRC staff made no regulatory decisions during the meeting.

Once received, the NRC staff will perform a thorough review of the proposed LAR and make any regulatory decisions in writing in a timely manner.

Public Meeting Feedback forms were available, but no comments were received.

The meeting adjourned at 10:37 a.m. (Eastern Standard Time).

Please direct any inquiries to me at 301-415-3100.

/RA/

John G. Lamb, Senior Project Manager Plant Licensing Branch, II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348, 50-364, 50-424 and 50-425

Enclosure:

List of Attendees cc w/encls: Distribution via Listserv

Pkg. ML21056A603 Meeting Notice ML21049A258 Meeting Summary ML21063A328 Meeting Slides ML21057A018 OFFICE DORL/LPL2-1/PM DORL/LPL2-1/LA DSS/SNSB/BC DORL/LPL2-1/BC DORL/LPL2-1/PM NAME JLamb KGoldstein SKrepel MMarkley JLamb DATE 03/4/2021 03/05/2021 03/8/2021 03/11/2021 03/12/2021 LIST OF ATTENDEES MARCH 4, 2021, PUBLIC MEETING WITH SOUTHERN NUCLEAR COMPANY REGARDING A PROPOSED LICENSE AMENDMENT REQUEST TO CHANGE THE TECHNICAL SPECIFICATION RELATED TO THE HEAT FLUX HOT CHANNEL FACTOR JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 ATTENDEE REPRESENTING John G. Lamb U. S. Nuclear Regulatory Commission (NRC)

Mike Markley NRC Matt Panicker NRC Shawn Williams NRC Summer Sun NRC Matt Hamm NRC Ben Parks NRC Ken Lowery Southern Nuclear Company (SNC)

Jamie Coleman SNC Matt Leonard SNC Enclosure