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MONTHYEARML19168A1692019-06-18018 June 2019
June 18 Public Meeting Slides (Exelon)
Project stage: Request
ML19176A0042019-07-15015 July 2019
Summary of Meeting with Exelon Generation Company, LLC, on a Planned License Amendment Request Regarding the Relaxation of Containment Differential Pressure Requirements
Project stage: Meeting
2019-06-18
[Table View] |
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Category:Meeting Summary
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Summary of November 16, 2021, Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Alternative to Extend the Inservice Inspection Interval
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ML20351A2832020-12-18018 December 2020
Summary of Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Exemption to Reduce the Frequency of Updates to Its Inservice Testing and Inspection Programs
ML20342A3522020-12-10010 December 2020
Summary of November 13, 2020, Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Alterantive to Certain Documentation Requirements for the Replacement of Pressure Retaining Bolting (EPID-L-2020-LRM-0102)
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Summary of November 4, 2020, Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Alternative to Reduce the Frequency of Updates to Its Inservice Testing and Inspection Programs
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and R.E. Ginna Nuclear Power Plant Summary of Meeting
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Summary of June 9, 2020, Pre-Submittal Meeting with Exelon Generation Company, LLC, Regarding Planned License Amendment Request to Modify Surveillance Requirement 3.6.1.3
ML19326C3582019-12-0303 December 2019
Summary of November 20, 2019, Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Revise the Quality Assurance Program
ML19326A3152019-12-0303 December 2019
Summary of November 18, 2019, Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Alternative to Supplemental Valve Position Indication Testing Requirements
ML19302F8772019-11-0404 November 2019
Summary of the October 28, 2019, Meeting with Exelon Generation Company, LLC, Regarding a Planned Supplement to a License Amendment Request Regarding Revising the Allowable Value for Reactor Water Cleanup System Isolation
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Summary of Meeting with Exelon Generation Company, LLC, on a Planned License Amendment Request Regarding the Relaxation of Containment Differential Pressure Requirements
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ML18347B4932019-01-0202 January 2019
Summary of Pre-Application Meeting with Exelon Generation Co., LLC (Exelon) Forthcoming License Amendment Requests to Revise Technical Specification Requirements for Main Steam Isolation Valve Leak Rate Tests
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Summary of June 5, 2018, Teleconference with Exelon Generation Company, LLC to Discuss Emergency Plan Changes at James A. Fitzpatrick Nuclear Power Plant and Nine Mile Point Nuclear Station
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Summary of Meeting with Exelon Generation Company, LLC Regarding Draft Guidance for Emergency Response Organization Staffing
ML18107A4972018-04-27027 April 2018
April 10, 2017, Summary of Public Meeting with Entergy Nuclear Operations, Inc. Regarding Upcoming License Amendment Request to Add Setpoint Verification Requirement to Technical Specification Surveillance Requirements
ML17256A7482017-09-28028 September 2017
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Summary Teleconference with Exelon Generation Company, LLC, on Planned Submittals of License Amendment Requests to Change Emergency Action Levels Associated with Lake Ontario Water Level
ML17143A3582017-05-23023 May 2017
Summary of Public Meeting for James A. Fitzpatrick and Nine Mile Point
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Public Meeting Handouts and Sign in Sheet
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Summary of Annual Assessment Meeting for James A. Fitzpatrick Nuclear Power Plant
ML15197A3332015-07-24024 July 2015
June 29, 2015 Summary of Meeting with Beyond Nuclear, Et. Al., Regarding Its 10 CFR 2.206 Petition Requesting Enforcement Action Against the James A. FitzPatrick Nuclear Power Plant
ML15120A0212015-04-28028 April 2015
April 23, 2015, Summary of Annual Assessment Meeting for James A. FitzPatrick Nuclear Power Plant on 4/23/2015
ML14197A5832014-09-18018 September 2014
Summary of the June 19, 2014, Category 1 Public Meeting with Entergy to Discuss Seismic Hazard Reevaluations Associated with Implementation of Japan Lessons-Learned Near-Tear Task Force Recommendation 2.1
ML14086A1532014-03-26026 March 2014
Summary of Annual Assessment Meeting for Nine Mile Point Nuclear Station and James A. FitzPatrick Nuclear Power Plant on 3/18/2014
ML13100A1172013-04-10010 April 2013
Summary of Public Meeting Regarding Nine Mile Point Nuclear Station and James A. Fitzpatrick Nuclear Power Plant
ML13162A5812012-07-19019 July 2012
PRB Closed Meeting Notes - 07/19/12 Gunter Et Al. 2.206 Requesting Enforcement Action Against James A. Fitzpatrick Plant
ML13162A5802012-05-29029 May 2012
PRB Closed Meeting Notes - 05/29/12 Gunter Et Al. 2.206 Requesting Enforcement Action Against James A. Fitzpatrick Plant
ML12102A1752012-04-11011 April 2012
and James A. FitzPatrick Nuclear Power Plant - Summary of Public Meeting on March 22, 2012
ML13162A6282012-03-20020 March 2012
by Larry Doerflein: PRB Notes Attached-Dial-In Provided
2023-09-22
[Table view] |
Text
July 15, 2019 LICENSEE: Exelon Generation Company, LLC FACILITY: James A. FitzPatrick Nuclear Power Plant
SUBJECT:
SUMMARY
OF JUNE 18, 2019, MEETING WITH EXELON GENERATION COMPANY, LLC, ON A PLANNED LICENSE AMENDMENT REQUEST REGARDING THE RELAXATION OF CONTAINMENT DIFFERENTIAL PRESSURE REQUIREMENTS AND THE MODIFICATION OF THE TORUS WATER LEVEL (EPID L-2019-LRM-0027)
On June 18, 2019, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Exelon Generation Company, LLC (Exelon, the licensee) at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss the licensees plan to submit a license amendment request regarding the relaxation of containment differential pressure requirements and the modification of the torus water level at the James A. FitzPatrick Nuclear Power Plant (FitzPatrick). The meeting notice and agenda, dated May 28, 2019, are available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML19154A262. A list of attendees is provided as Enclosure 1.
The licensee presented an overview of its plans to submit the license amendment request for FitzPatrick. The presentation closely followed Exelons slides provided for the meeting (ADAMS Accession No. ML19168A169).
The licensee stated that the amendment request will contain two separate change requests: the relaxation of containment differential pressure requirements and the modification of the torus water level. The licensee stated that the results of the various testing and calculations will be included and that additional details will be available to the NRC staff for review. The licensee plans on providing a workbook to assist the staff review, which will include, among other items, background information and General Electric Report 005N1724, Short-Term Containment Analysis for Zero Drywell-to-Wetwell Pressure Differential, dated May 2019. The licensee has had success with this approach previously.
The NRC staff provided some feedback to the licensee, including the following:
The licensee should consider including the following in its application:
General Electric Report 005N1724 Methods, assumptions, and results of short-term containment pressure response, temperature response for equipment qualification for equipment inside the containment, and containment wall temperature for structural analysis, and the short and long-term net positive suction head analysis
Methods, assumptions. and results of vent thrust loads, pool swell, condensation oscillation, and chugging analyses Methods, assumptions, and the results of analysis of the loading on the torus walls, and structural analysis of the piping and components inside the torus due to mass and energy release from a design-basis loss of coolant accident and safety relive valve discharge A markup for the FitzPatrick Updated Final Safety Analysis Report The licensee should consider providing a summary of the calculation methodology and how the calculation meets the guidance of Regulatory Guide 1.105, Setpoints for Safety-Related Instrumentation, and Regulatory Issue Summary 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. At a minimum, the calculation summary should include the safety limit, the analytical value, total loop error, limiting setpoint, nominal trip setpoint, allowable value, and as-left and as-found limits.
The licensee should identify if it has adopted Technical Specifications Task Force (TSTF) Traveler TSTF-493, Clarify Application of Setpoint Methodology for LSSS
[Limiting Safety System Settings] Functions. If TSTF-493 has been adopted, the relevant notes should be added to the FitzPatrick Technical Specifications regarding as-left and as-found tolerances, or a justification should be provided for not adding the notes.
The schedule currently calls for the license amendment request to be submitted by the end of August 2019.
Members of the public were not in attendance. Public Meeting Feedback forms were not received.
Please direct any inquiries to me at 301-415-1603 or Carleen.Parker@nrc.gov.
/RA/
Carleen J. Parker, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosure:
List of Attendees cc: Listserv
LIST OF ATTENDEES JUNE 18, 2019, MEETING WITH EXELON GENERATION COMPANY, LLC PLANNED LICENSE AMENDMENT REQUEST REGARDING THE RELAXATION OF CONTAINMENT DIFFERENTIAL PRESSURE REQUIREMENTS AND THE MODIFICATION OF THE TORUS LEVEL NRC Participants Carleen Parker Calvin Cheung Ahsan Sallman Nagesware Karipineni Gursharan Singh Jerome Bettle Exelon Participants Bill Drews Jason Ritzel Thomas Yurkon Dave Burch Christian Williams Shane Gardner Raymond Paige (Imperia Engineering Partners)
Enclosure
ML19176A004 OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DORL/LPL1/BC NRR/DORL/LPL1/PM NAME CParker LRonewicz JDanna CParker DATE 07/09/2019 07/08/2019 07/10/2019 07/15/2019
