ML21047A262
| ML21047A262 | |
| Person / Time | |
|---|---|
| Site: | Vogtle, Farley  |
| Issue date: | 02/19/2021 |
| From: | John Lamb Plant Licensing Branch II |
| To: | Southern Nuclear Operating Co |
| Lamb J | |
| Shared Package | |
| ML21036A137 | List: |
| References | |
| EPID L-2021-LRM-0011 | |
| Download: ML21047A262 (6) | |
Text
February 19, 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
SUBJECT:
SUMMARY
OF FEBRUARY 16, 2021, PUBLIC MEETING WITH SOUTHERN NUCLEAR OPERATING COMPANY, INC., REGARDING A PROPOSED LICENSE AMENDMENT REQUEST TO CHANGE THE CORE POWER DISTRIBUTION MONITORING SYSTEM FOR JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2, AND VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 (EPID NO. L-2021-LRM-0011)
On February 16, 2021, 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 on-line core power distribution monitoring system (PDMS) for performing technical specification (TS) surveillances of core thermal limits for Joseph M. Farley Nuclear Plant (Farley), Units 1 and 2, and Vogtle Electric Generating Plant (Vogtle), Units 1 and 2.
A list of attendees is provided as an Enclosure.
On February 5, 2021 (Agencywide Document and Access Management System (ADAMS)
Accession No. ML21036A338), the meeting was noticed on the NRC public webpage.
The SNC presented slides contained in ADAMS Accession No. ML21036A117.
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 on the Best Estimate Analyzer for Core Operations - Nuclear (BEACONTM) Technical Specification Monitor (TSM),
and (2) the proposed LAR.
Background
SNC representatives stated that the core power distribution information is used to verify to following core parameters: (1) control rod position (Technical Specification (TS) 3.1.7), (2) heat flux hot channel factor (TS 3.2.1), (3) nuclear enthalpy rise hot channel factor (TS 3.2.2), (4) quadrant power tilt ratio (QPTR) (TS 3.2.4), and (5) axial flux difference (AFD) for calibration of OTT reactor trip function (TS 3.3.1). SNC said that the core power distribution information is
typically obtained by taking a monthly flux map using the Movable Incore Detector System (MIDS).
Westinghouse developed the BEACON' system to improve operational support for pressurized-water reactors (PWRs). It is a core monitoring and support package that uses Westinghouse standard instrumentation in conjunction with an analytical methodology for online generation of three-dimensional power distributions. The system provides the following for the core: monitoring, measurement reduction, analysis, and predictions.
BEACON' Online Monitor (OLM) adds capability to calculate estimated critical condition, shutdown margin, load swing and other reactor engineering support functions plus on-line monitoring of core power distribution using core exit thermocouple data with no calculation of online uncertainties.
BEACON' TSM has all the functions of BEACON' OLM plus TS monitoring. BEACONTM TSM calculates online dynamic uncertainties based on instrumentation characteristics and time since the last flux map, plus allows the user to perform power distribution surveillances without taking a flux map using only the available instrumentation.
SNC stated that advantages of using the BEACON'-TSM application of the core power distribution monitoring system (PDMS) include: (1) essentially continuous monitoring of the core power distribution, and (2) flux maps using MIDS only required for BEACON' calibration. SNC said that MIDS flux maps typically performed every 31 effective full power days (EFPD), and will allow extending performance of MIDS flux maps using up to 180 EFPD.
Proposed LAR SNC representatives stated that the following TSs explicitly mention using MIDs or flux maps:
(1) TS 3.1.7 Rod Position Indication, (2) TS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z)), (3) TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNH), (4) TS 3.2.4 Quadrant Power Tilt Ratio (QPTR), and (5) TS 3.3.1 Reactor Trip System (RTS) Instrumentation. SNC stated that it plans to revise TS to refer to using core power distribution information, and the functionality requirements for the BEACON PDMS will be included in the SNC owner-controlled Technical Requirements Manual (TRM) and implemented in plant procedures.
SNC representatives stated that the following plants have implemented BEACON'-TSM amendments:
(1) V. C. Summer, Amendment 142, April 9, 1999 (ADAMS Accession No. ML012260068),
(2) Salem Units 1 and 2, Amendments 237 (Unit 1) and 218 (Unit 2), November 6, 2000, (ADAMS Accession Nos. ML003761792 and ML003767901),
(3) Diablo Canyon Units 1 and 2, Amendments 164 (Unit 1) and 166 Unit 2, March 31, 2004, (ADAMS Accession No. ML040920245),
(4) South Texas Project Units 1 and 2, Amendments 175 (Unit 1) and 163 (Unit 2),
March 31, 2006 (ADAMS Accession Nos. ML060760501 and ML060950451),
(5) Callaway, Amendment 182, March 21, 2007, (ADAMS Accession Nos. ML070460584 and ML070680350),
(6) Commanche Peak Units 1 and 2, Amendments 144 (Unit 1) and 144 (Unit 2),
April 2, 2008, (ADAMS Accession Number ML080510083/ML080500627),
(7) Watts Bar Unit 1, Amendment 82, October 27, 2009, (ADAMS Accession Number ML092710381),
(8) Wolf Creek, Amendment 188, July 23, 2010, (ADAMS Accession Number ML100820517), and (9) Prairie Island Units 1 and 2, Amendments 201 (Unit 1) and 188 (Unit 2), May 4, 2011, (ADAMS Accession Number ML103430498).
SNC representatives stated that it plans a proposed LAR to adopt a new on-line core PDMS for performing TS surveillances of core thermal limits at Farley and Vogtle. SNC said that the new monitoring system is called BEACONTM TSM. The licensee also stated that the current monitoring system used at both Farley and Vogtle plants is BEACONTM OLM. The licensee stated that Farley and Vogtle will have the option of determining TS required core power distribution information without using moveable incore detectors (MIDs), provided the BEACONTM TSM calibration requirements have been satisfied, and if the proposed LAR is approved. SNC representatives said that the scope of the proposed LAR will be similar to the Prairie Island Nuclear Generating Plant, Units 1 and 2, amendments approved by letter dated May 4, 2011 (ADAMS Accession No. ML103430498).
SNC representatives stated that the proposed LAR will provide a high-level overview on WCAP-12472-P BEACON Core Monitoring and Operations Support System. SNC representatives said that the proposed LAR will discuss temperature and neutron monitoring used to generate power distribution, and the submittal will discuss the SPNOVA 3-D neutronics analysis Code originally used in BEACONTM as well as the 3-D Advanced Nodal Code (ANC). The licensee stated that the proposed LAR will discuss the minimum monitoring requirements per WCAP, and how the conditions from the WCAP safety evaluation report (SER) will be met. SNC representatives said that the NRC has approved four addenda to WCAP-12472-P-A, and the proposed LAR will discuss each addendum, and the applicability to Farley and Vogtle.
NRC Questions to SNC The NRC staff asked about the uncertainty calculations. SNC representatives said that the uncertainty would be discussed in the submittal. The NRC staff questioned the specific approval that SNC would be requesting. SNC stated that it will request approval of the BEACONTM TSM only, and the BEACONTM PDMS will be moved to the TRM. The NRC staff asked about the limitations and conditions of WCAP-12472-P-A. SNC said that the submittal will contain a discussion of how SNC meets the limitations and conditions from the WCAP-12472-P-A for Farley and Vogtle. The NRC staff questioned when the proposed LAR will be submitted and what will be the requested review date. SNC stated that the proposed LAR should be submitted in approximately May 2021, and SNC will request the review to be completed in 12 months.
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 10:28 am (Eastern 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: Listserv
LIST OF ATTENDEES FEBRUARY 16, 2021, PUBLIC MEETING WITH SOUTHERN NUCLEAR COMPANY REGARDING A PROPOSED LICENSE AMENDMENT REQUEST TO CHANGE THE CORE POWER DISTRIBUTION MONITORING SYSTEM JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 ATTENDEE REPRESENTING John G. Lamb NRC Matt Panicker NRC Shawn Williams NRC Kevin Heller NRC Robert Lukes NRC Josh Borromeo NRC Charley Peabody NRC Stephanie Devlin-Gill NRC Ryan Joyce SNC Bob Florian SNC Jennifer Baker SNC Jamie Coleman SNC Bob Sears SNC Wes Sparkman SNC James Farr SNC Matt Leonard SNC Enclosure
ML21036A137 (Package)
ML21036A338 (Meeting Notice)
ML21047A262 (Meeting Summary)
ML21036A117 (Slides)
OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DSS/SFNB/BC NAME JLamb KGoldstein RLukes DATE 02/16/2021 02/17/2021 02/16/2021 OFFICE NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME MMarkley JLamb DATE 02/18/2021 02/19/2021