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Category:Meeting Summary
MONTHYEARML24226B2112024-08-22022 August 2024 Regulatory Audit Summary in Support of License Amendment Requests to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions ML24213A2462024-08-0505 August 2024 Summary of Closed Meeting SNC Fleet - Physical Barriers Exemption ML24198A0772024-07-18018 July 2024 Summary of Observation Public Meeting Held with SNC Regarding Previous LAR to Revise TS 3.6.5 Completion Time Increase Using Risk-Informed Process for Evaluation to Increase for Farley Nuclear Plant, Units 1 and 2 ML24156A1772024-06-11011 June 2024 Summary of June 6, 2024, Closed Meeting Held with Southern Nuclear Operating Company, Inc., Regarding the Physical Barrier Exemptions for Joseph M. Farley Nuclear Plant, Units 1 and 2, Edwin I. Hatch Nuclear Plant, Units 1 and 2, and Vogtle ML24138A0092024-05-17017 May 2024 Public Meeting Summary - 2023 Annual Assessment Meeting for Joseph M. Farley, Units 1 and 2 Docket No. 50-348, and 50-364 -Meeting Number 20240474 ML24093A0612024-04-18018 April 2024 April 1, 2024, Summary of Observation Pre-Submittal Meeting Held with Southern Nuclear Operating Company, Inc., Proposed Alternative Requests to the Extend Examination Intervals for Joseph M. Farley Nuclear Plant and Vogtle ML24096A1832024-04-12012 April 2024 Summary of April 3, 2024, Observation Pre-Submittal Meeting Held with Southern Nuclear Operating Company, Inc., Regarding Proposed License Amendment Request to Revise Technical Specification 3.6.5 ML24019A1932024-01-30030 January 2024 Summary of January 8, 2024, Observation Pre-Submittal Meeting Held with Southern Nuclear Operating Company Regarding a Proposed LAR for Vogtle Electric Generating Plant, Units 1, 2, 3, & 4; Hatch, Units 1 & 2; Farley, Units 1 & 2 ML23356A0282023-12-27027 December 2023 December 11, 2023, Pre-Application Meeting with SNC Regarding a Proposed Fleet LAR to Revise TS 5.3.1 to Relocate Training Qualification Requirements from TS to Their Qatr/Ndqam ML23311A1302023-11-17017 November 2023 Summary of Nov. 6, 2023, - Closed Meeting Held with Southern Nuclear Operating Company, Inc., Regarding Physical Barriers Exemptions for Hatch Units 1 & 2, Farley Units 1 & 2 and Vogtle Units 1, 2, 3 & 4 (EPID L-2023-LLE-0018 & L-2023-LLE-0 ML23146A1672023-05-31031 May 2023 Public Meeting Summary2022 Annual Assessment Meeting for Joseph M. Farley, Units 1 and 2 Docket No. 50?348, and 50?364 Meeting Number 20230610 ML23094A1092023-04-14014 April 2023 Summary of Conference Call Held with SNC, Regarding Regulatory Issue Summary 2000-11, Supplement 2, NRC Emergency Telecommunications System, for Joseph M. Farley Nuclear Plant, Units 1 and 2, and SNC Emergency Operations Facility ML22172A2142022-07-11011 July 2022 June 16, 2022, Summary of Public Meeting with Southern Nuclear Operating Company, Inc., a Proposed License Amendment Request to Modify the Technical Specifications Regarding Pressurizer Safety Valve Setpoints at the Joseph M. Farley Nuclear ML22108A1382022-04-18018 April 2022 Annual Assessment Public Meeting Summary ML21313A1172021-11-18018 November 2021 Summary of Public Meeting with Southern Nuclear Operating Company, Inc., Regarding a Proposed License Amendment Request to Change the Technical Specification Related to Technical Specification 5.5.16 for Joseph M. Farley Nuclear Plant ML21288A3312021-11-0404 November 2021 Summary of October 14, 2021, Public Meeting with SNC, Inc., Regarding Proposed LAR to Modify the TSs to Increase Containment Peak Pressure to Address Several Nuclear Safety Advisory Letters L-2021-LRM-0097 ML21176A1712021-07-0606 July 2021 Summary of June 24, 2021, Public Meeting Regarding a Proposed LAR to Permanently Remove the Encapsulation Vessels Around Containment Sump Recirculation Valves ML21124A1232021-05-0404 May 2021 April 27, 2021, Public Meeting Summary Joseph M. Farley Nuclear Plant Units 1 and 2, Edwin I. Hatch Nuclear Plant Units 1 and 2, Docket No. 50-348, 50-364, 50-321, 50-366, Meeting Number ML21117A030 ML21102A3112021-04-19019 April 2021 Corrected - 03/31/2021 Summary of Public Meeting with Southern Nuclear Operating Company, Inc., Regarding a Proposed Licensing Action Request to Change the Quality Assurance Topical Report ML21092A0082021-04-0808 April 2021 Summary of March 31, 2021, Public Meeting with Southern Nuclear Operating Company, Inc., Regarding a Proposed Licensing Action Request to Change the Technical Specification Related to Heat Flux Hot Channel Factor ML21063A3282021-03-12012 March 2021 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 ML21047A2622021-02-19019 February 2021 Summary of Public Meeting with Southern Nuclear Operating Company, Inc., Regarding a Proposed License Amendment Request to Change the Core Power Distribution Monitoring System ML20318A0752020-11-16016 November 2020 Summary of November 12, 2020, Public Meeting with Southern Nuclear Operating Company, Inc., Regarding a License Amendment Request for the Emergency Plan ML20217L3692020-08-13013 August 2020 Summary of Meeting Joseph M. Farley Nuclear Plant, Units 1 and 2; Edwin I. Hatch, Units 1 and 2; and Vogtle Electric Generating Plant, Units 1, 2, 3, and 4 a LAR for the Emergency Plan (EPID Nos. L-2020-LLA0150 and L-2020-LLA-015 ML20154K7242020-06-0202 June 2020 EOC Meeting Summary ML19149A4222019-05-29029 May 2019 Summary of Public Meeting Concerning Annual Assessment of the Farley Nuclear Plant, Units 1 and 2, Docket Nos. 05000348 and 05000361 ML19059A3672019-03-0707 March 2019 March 5, 2019, Meeting Summary Regarding Pre-Application Meeting to Discuss Proposed Amendment to Revise Technical Specification 3.3.1 and 3.3.2 ML19038A3462019-02-15015 February 2019 Summary of Meeting with the Nuclear Regulatory Commission and Southern Nuclear Operating Company, Inc. Regarding Pre-Submittal of a License Amendment Request for Proposed Changes to Emergency Response Organization Staffing and Augmentation ML18318A2532018-11-26026 November 2018 Summary of Pre-Application Meeting to Discuss the Joseph M. Farley Nuclear Plant, Units 1 and 2, Spent Fuel Pool Criticality Analyses and Measurement Uncertainty Recapture Amendments ML18306A3132018-11-0707 November 2018 Summary of October 16, 2018, Meeting with Southern Nuclear Operating Company, Inc., to Discuss the Joseph M. Farley Unit 1 & 2, Electrical Distribution System as It Relates to the Risk-Informed Completion Times Amendment ML18284A0222018-10-16016 October 2018 August 23, 2018, Summary of Pre-Application Meeting with Southern Nuclear Operating Company, Inc. to Discuss TSTF-51 and TSTF-471 ML18142B0452018-05-24024 May 2018 Summary of May 21, 2018, Pre-submittal Public Teleconference with Southern Nuclear Operating Company, Inc. to Discuss the Upcoming License Amendment Request to Remove the Dedicated Shift Technical Advisor ML18110A3302018-04-20020 April 2018 Public Meeting Summary - Farley Nuclear Plant Docket Nos. 50-348, 50-364 ML17276A0862018-03-16016 March 2018 Summary of March 12, 2018, Pre-Application Meeting with Southern Nuclear Company, Inc., to Discuss a Future Risk-Informed Completion Times Amendment ML17104A1382017-04-14014 April 2017 Summary of Meeting to Discuss the Annual Assessment of Farley Nuclear Plant, Units 1 and 2 ML16237A0612016-10-0404 October 2016 Summary of Pre-Application Meeting with Southern Nuclear Operating Company to Discuss an Alternative Source Term Submittal ML16126A0812016-05-0505 May 2016 Summary of Public Meeting with Joseph M. Farley, Units 1 and 2 ML15125A0872015-05-26026 May 2015 May 12, 2015 Summary of Meeting with Southern Nuclear Operating Company to Discuss a Future Fleet Standard Emergency Plan Submittal ML15120A5942015-04-30030 April 2015 Summary of Public Meeting to Discuss 2014 Annual Performance Assessment of the Joseph M. Farley Nuclear Plant ML15103A0602015-04-30030 April 2015 April 22, 2015, Summary of Meeting with Southern Nuclear Operating Company to Discuss a Future Fleet Standard Emergency Plan Submittal ML15092A2432015-04-22022 April 2015 Summary of Telephone Conference Call Held on November 19, 2014, Between the U.S. Nuclear Regulatory Commission and DTE Electric Concerning Set 7 - November 19, 2014 ML15092A1142015-04-10010 April 2015 March 4, 2015, Summary of Meeting Between Representatives of the U.S. Army Corps of Engineers, Nuclear Regulatory Commission, and Southern Nuclear Operating Company, Inc. to Discuss Flooding Analysis Associated with Joseph M. Farley Nuclear ML15043A4592015-02-24024 February 2015 Summary of Site Audit to Support the Review of a License Amendment Request for Joseph M. Farley Nuclear Plant, Units 1 and 2, to Transition to the National Fire Protection Association Standard 805 Fire Protection Licensing Basis ML14197A5932014-08-0606 August 2014 June 26, 2014, Summary of Category 1 Public Meeting with Southern Nuclear Operating Company to Discuss Seismic Hazard Reevaluations Associated with Implementation of Japan Lessons-Learned Near-Term Task Force Recommendation 2.1 ML14133A0392014-06-0303 June 2014 Summary of Closed Meeting Between Representatives of the Army Corps of Engineers, Nuclear Regulatory Commission, and Southern Nuclear Company to Discuss Dam Failure for the Joseph Farley Nuclear Plant ML14134A0312014-05-22022 May 2014 Summary of May 16, 2014, Meeting with Southern Nuclear Operating Company to Discuss the Joseph M. Farley Flooding Hazard Reevaluation Extension Request ML14122A0372014-05-0808 May 2014 April 23, 2014 Summary of Meeting with Southern Nuclear Operating Company to Discuss Grid Design Criteria ML14108A3762014-05-0808 May 2014 Summary of Meeting with Southern Nuclear Operating Company to Discuss Deletion of the Residual Heat Removal Autoclosure Interlock ML14115A4052014-04-25025 April 2014 2013 End of Cycle Farley Public Meeting Summary Memo ML13225A2932013-08-12012 August 2013 7/23-24/2013, Summary of Meeting 2013 U.S. Nuclear Regulatory Commission (NRC) Initial Exam Writers' Workshop 2024-08-05
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July 6, 2021 LICENSEE: Southern Nuclear Operating Company, Inc.
FACILITY: Joseph M. Farley Nuclear Plant, Units 1 and 2
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 -
SUMMARY
OF PUBLIC MEETING ON JUNE 24, 2021, REGARDING PROPOSED LICENSE AMENDMENT REQUEST TO PERMANENTLY REMOVE THE ENCAPSULATION VESSELS AROUND CONTAINMENT SUMP RECIRCULATION VALVES (EPID L-2021-LRM-0058)
On June 24, 2021, an Observation 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 to discuss a proposed future license amendment request (LAR) to permanently remove the encapsulation vessels around containment recirculation suction valves at the Joseph M. Farley Nuclear Plant, Units 1 and 2 (Farley).
A list of attendees is provided as an Enclosure.
On June 7, 2021 (Agencywide Document and Access Management System (ADAMS)
Accession No. ML21158A226), the meeting was noticed on the NRC public webpage for the meeting to be held on June 24, 2021.
The SNC presented slides contained in ADAMS Accession No. ML21173A063.
Introduction The NRC staff opened the meeting with introductory remarks and introduction of the attendees.
The SNC staff discussed the following topics: (1) LAR summary description, (2) system design and operation, (3) current licensing basis requirements, (4) reason for proposed change, (5) description of proposed change, and (6) technical evaluation of proposed change.
Background
The SNC staff stated that it plans to request a license amendment to permanently remove encapsulation vessels and associated guard piping installed around the first Containment Spray (CS) and first Residual Heat Removal (RHR) / Low Head Safety Injection (LHSI) motor-operated gate isolation valves and the upstream suction piping. The recirculation suction lines for CS and RHR/LHSI from the containment sump have two isolation valves in each line that are outside of containment. The first isolation valve in each line, the valve nearest to containment, is enclosed in a metal housing to collect leakage out of the valve. SNC stated that the LAR would propose to change the licensing basis from relying on the valve encapsulation to collect leakage to
relying on the design of the valve and piping to preclude leakage and the capability of detecting and terminating leakage from the valve packing or bonnet seals.
Proposed License Amendment Request SNC stated that it determined that the proposed change would involve a more than minimal increase in the likelihood of occurrence of a malfunction of a structure, system, or component (SSC) important to safety previously evaluated in the updated final safety analysis report, (UFSAR) (per Title 10 of the Code of Federal Regulations [10 CFR], Part 50.59(c)(2)(ii)).
Therefore, SNC plans to submit a proposed LAR to request NRC approval of the change.
SNC stated that the proposed LAR would describe a change to the Farley licensing basis, as described in the UFSAR, to allow permanent removal of the encapsulation vessels around the first isolation valves in the recirculation suction lines for the CS and RHR/LHSI systems and the associated guard piping. SNC stated that the proposed design will be in accordance with the acceptance criteria in NRC review guidance in NUREG-0800, Standard Review Plan [SRP],
Section 6.2.4 Containment Isolation System, Revision 3 (ADAMS Accession No. ML070380197), and meet the applicable requirements in Appendix A, General Design Criteria for Nuclear Power Plants (GDC), to 10 CFR Part 50. SNC stated that the existing encapsulations and guard piping are credited to meet the GDC-56, Primary Containment Isolation, and the licensees proposed method for meeting GDC-56 is consistent with American National Standards Institute (ANSI) N271-1976, Section 3.6.5 that is endorsed by NRC Regulatory Guide (RG) 1.141, Containment Isolation Provisions for Fluid Systems. The NRC Staff noted that the current version of RG 1.141 is Revision 1 (ADAMS Accession No. ML092850042) and suggested the amendments reference the applicable version in the submittal.
SNC stated that the initial licensing basis of some plants did not include CS and RHR encapsulations. SNC indicated it was unaware of any previous reviews where credited encapsulations were removed and stated that its submittal would likely be a first-of-a-kind LAR review.
SNC stated that it plans to submit the LAR in July or August 2021 and would request that the NRC staff complete its review by March 2022 to support removing the first encapsulations in the spring 2022 outage for Unit 2.
NRC Questions to SNC The NRC staff had questions on slides 5, 7, 8, 13, 15, 19, and 21-23.
The NRC staff questioned the licensees 10 CFR 50.59 determination of the more than minimal increase in the likelihood of occurrence of a malfunction of an SSC important to safety previously evaluated in the UFSAR and requested to understand more about the aspects of proposed change that are not determined to be more than minimal, which SNC plans to address separately, outside the scope of the proposed LAR. The licensee did not elaborate on what those other changes may be as the 10 CFR 50.59 screenings are not yet complete.
The NRC staff questioned SNCs proposed submittal and review schedule and asked if the piping stress analyses will be included in the proposed LAR. SNC described its proposed review schedule of July or August 2021, to March 2022, which is an approximately seven-month review schedule, including the Acceptance Review. SNC stated that the piping stress analyses
is currently being performed and that SNC plans to make the analyses available to the NRC staff via audit but would not expect to submit it as an attachment or enclosure to its LAR submittal. The NRC staff informed SNC that its proposed seven-month review schedule may be challenging and is short for a first-of-a-kind LAR review particularly if it is known to require an audit prior to submittal. The NRC clarified that any information relied on in its safety evaluation would need to be submitted on the docket and suggested as much information as possible be submitted in the licensees LAR.
The NRC staff questioned whether the valve encapsulations were credited for containment isolation and SNC responded that the valve encapsulations were not credited for containment isolation but used to collect potential leakage.
The NRC staff questioned dose rates in the area supporting the licensees assertion that the proposed change would save radiation exposure. The licensee acknowledged that it was mostly an outage labor issue but reiterated that there would be some dose savings. The NRC staff requested that SNC include information in its submittal concerning: radiation exposure estimates including control room dose; impacts related to SNCs approved10 CFR 50.67 Accident source term, and explanation how SNCs analysis is still bounding; and a description of the safety benefit of the proposed change.
The NRC staff asked questions about the assumptions and evaluation methodology that SNC will use to explain that the containment emergency sump suction lines, up to and including the first isolation valve, meet or exceed the piping stress analyses requirements and methodology described in Branch Technical Position (BTP) 3-4, Postulated Rupture Locations in Fluid System Piping Inside and Outside Containment, Revision 3 (ADAMS Accession No. ML16085A315). SNC stated that the piping included in the stress analyses is assumed to be no more than moderate-energy piping, not high-energy piping. The NRC staff requested that SNC consider the NRC review guidance described in BTP3-4, including equations, parameter assumptions, and the results of the analyses.
SNC responded to the NRCs comments and questions and stated that the pre-licensing meeting feedback would be considered as it develops the submittal.
Closing The NRC staff made no regulatory decisions during the meeting.
There were no members of the public in attendance.
Please direct any inquiries to me at 301-415-1009.
/RA/
Shawn Williams, Senior Project Manager Plant Licensing Branch, II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364
Enclosure:
List of Attendees cc : Listserv
LIST OF ATTENDEES JUNE 24, 2021, PUBLIC MEETING WITH SOUTHERN NUCLEAR COMPANY REGARDING A PROPOSED LICENSE AMENDMENT REQUEST JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 ATTENDEE REPRESENTING Stephanie Devlin-Gill U.S. Nuclear Regulatory Commission (NRC)
Ravi Grover NRC Dawnmathews Kalathiveettil NRC Chang Li NRC Yueh-Li Li NRC Mike Markley NRC Sean Meighan NRC Peter Meier NRC Steve Smith NRC Ian Tseng NRC Tristan Villareal NRC Shawn Williams NRC Jamie Marquess Coleman Southern Nuclear Operating Company (SNC)
William Evans SNC Cheryl Ann Gayheart SNC Ryan Joyce SNC Thomas McCallum SNC Daniel Shutt SNC Wesley Sparkman SNC Stephen Swantner SNC Steve Berryhill SNC Kate Barnett SNC Keith Brown SNC James Andrachek SNC Enclosure
ML21176A171 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NAME SDevlin-Gill SWilliams KGoldstein DATE 6/25/2021 7/2/2021 7/1/2021 OFFICE NRR/DSS/SCPB/BC NRR/DSS/STSB/ABC NRR/DRA/ARCB/BC NAME BWittick NJordan KHsueh DATE 6/25/2021 6/28/2021 6/30/2021 OFFICE NRR/DEX/EMIB/ABC NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME ITseng MMarkley SWilliams DATE 6/28/2021 7/6/2021 7/6/2021