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Category:Meeting Summary
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Summary of Public Meeting with Constellation Energy Generation, LLC Regarding Hooded Masks
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Constellation - Summary of November 14, 2023, Public Pre-Application Meeting with Constellation Energy Generation, LLC on Adoption of TSTF-591
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September 25, 2023, Summary of with Constellation Energy Generation, LLC on Proposed Changes to Emergency Plans
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R. E. Ginna Nuclear Power Plant - Constellation - Pre-Application Amse 9/18/2023 Meeting Summary
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6/7/2023 - Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - Meeting Summary
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Summary of February 23, 2023, with Constellation Energy Generation, LLC on Proposed Changes to Emergency Plans to Revise Emergency Action Levels
ML22187A1462022-07-0606 July 2022
Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - 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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Summary of the July 27, 2021, Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Use Case OMN-28,
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June 15, 2021, Summary of Meeting with Exelon Generation Company, LLC Vessel Nozzle Repair Related to a Planned Request for an Alternative Related to Reactor Pressure
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Summary of Meeting with Exelon Generation Company, LLC Regarding Its Requested Alternative to Eliminate Certain Documentation Requirements for the Replacement of Pressure Retaining Bolting
ML21011A2822021-01-21021 January 2021
Summary of January 6, 2021, Presubmittal Meeting Between the NRC and Exelon Generation Company, LLC Regarding Licensing Activities to Support the Planned Early Closures of Byron, Unit Nos. 1 and 2 and Dresden, Units 2 and 3
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
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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)
ML20323A0332020-12-0101 December 2020
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
ML20163A1722020-06-12012 June 2020
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
ML19291A0022019-11-0101 November 2019
10/03-10/08/2019 Summary of Meetings with Exelon Generation Company, LLC, on Emergency Amendment Request Regarding One-Time Extension to Technical Specifications 3.8.1 Action A.3 Completion Time for Inoperable Offsite Source (EPID L-2019-LL
ML19302D3152019-10-28028 October 2019
Annual Assessment Meeting for James A. Fitzpatrick Nuclear Power Plant and Nine Mile Point Nuclear Generating Station - Meeting Summary
ML19183A1282019-07-15015 July 2019
Summary of June 20, 2019, Meeting with Exelon Generation Company, LLC, on a Planned License Amendment Request Regarding Main Steam Isolation Valve Leak Rate Increase Utilizing
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
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Summary of June 4, 2019, Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Extend the Test Interval for Safety Relief Valves
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Summary of Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Use ASME Code Case N-879
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Summary of December 19, 2018, Meeting with Exelon Generation Company, LLC Regarding the Use of Boiling Water Reactor Vessel and Internals Project Guidelines
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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
ML18325A1712018-11-28028 November 2018
Summary of Meeting with Exelon Generation Company, LLC Regarding Planned Fleet License Amendment Request to Revise Technical Specifications for High Radiation Areas
ML18304A1662018-11-0606 November 2018
Summary of October 23, 2018, Teleconference with Exelon Generation Co., LLC to Discuss Potential License Amendment Request Ultimate Heat Sink Bar Rack Bar Heaters
ML18297A1722018-10-26026 October 2018
Summary of Meeting with Exelon Generation Company, LLC Regarding Planned License Amendment Request to Adopt TSTF-427
ML18262A3662018-09-18018 September 2018
August 21, 2018, James A. Fitzpatrick Nuclear Power Plant (Fitzpatrick) and Nine Mile Point Nuclear Generating Station (Nine Mile Point) Summary of Public Meeting
ML18163A2682018-06-19019 June 2018
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
ML18120A1772018-05-0101 May 2018
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
Summary of September 5, 2017, Meeting with Exelon Generation Co., LLC to Discuss Potential License Amendment Request Technical Specifications Task Force Traveler TSTF-542, Revision 2, for James A. Fitzpatrick Nuclear Power Plant
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Notice of Meeting with Florida Power & Light Company and NextEra Energy to Discuss Closing Out Generic Safety Issue-191 and Generic Letter 2004-02
ML17144A2852017-06-0202 June 2017
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
ML17143A1902017-05-23023 May 2017
Public Meeting Handouts and Sign in Sheet
ML17143A3582017-05-23023 May 2017
Summary of Public Meeting for James A. Fitzpatrick and Nine Mile Point
ML17031A2802017-02-0808 February 2017
Summary of Teleconference with Entergy Nuclear Operations, Inc. Regarding Verbal Authorization for Relief Request RR-21 for the James A. Fitzpatrick Nuclear Power Plant
ML16229A4542016-08-16016 August 2016
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
2024-06-03
[Table view] |
Text
July 15, 2019 LICENSEE: Exelon Generation Company, LLC FACILITY: James A. FitzPatrick Nuclear Power Plant
SUBJECT:
SUMMARY
OF JUNE 20, 2019, MEETING WITH EXELON GENERATION COMPANY, LLC, ON A PLANNED LICENSE AMENDMENT REQUEST REGARDING MAIN STEAM ISOLATION VALVE LEAK RATE INCREASE UTILIZING ALTERNATE SOURCE TERM ANALYSIS (EPID L-2019-LRM-0032)
On June 20, 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 (LAR) regarding main steam isolation valve leak rate increase utilizing alternate source term (AST) analysis 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. ML19156A264. A list of attendees is enclosed.
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. ML19168A159).
The licensee stated that FitzPatrick currently has a partial AST approved for fuel handing accidents only. The planned LAR would request to expand the AST scope to full implementation and include an increase in main steam isolation valve local leak rate testing limits and addition of a secondary containment drawdown time. The licensee stated that the loss-of-coolant analysis and the Gothic computer code analysis will be provided as part of the LAR. The licensee stated that there are no planned physical equipment modifications for this request. The licensee is using the Quad Cities Nuclear Power Station, Units 1 and 2, application dated March 5, 2019, as precedent (ADAMS Accession No. ML19064B369). The Quad Cities Nuclear Power Station, Units 1 and 2, application is currently under NRC review.
The NRC staff provided some feedback to the licensee, including the following:
When referencing precedence, discuss how it is applicable to FitzPatrick.
The licensee should consider including a discussion of the meteorological data in the LAR.
When providing dose information, it is helpful to provide the dose value for each pathway in addition to the total dose.
Since the FitzPatrick licensing basis does not currently credit drywell sprays for aerosol removal, the licensee should consider including a detailed description of the proposed change to add credit for drywell sprays to the licensing basis.
Since the precedent cited for the proposed main steam line aerosol deposition did not include drywell sprays, the licensee should consider including a detailed discussion of how the use of sprays is accounted for in the subsequent steam line aerosol deposition.
The inclusion of a comparison of the dose with credit for sprays and steam line deposition to the dose without these aerosol deposition credits would be helpful for the NRC staffs review.
The licensee should consider including if the current environmental qualification of equipment is bounding or if testing/analysis was utilized or if the environment is mild.
The licensee should consider addressing control room access, specifically how Title 10 of the Code of Federal Regulations (10 CFR) Part 50.67, Accident source term, and General Design Criteria 19, Control Room, will continue to be met.
The licensee needs to address the requirements contained in 10 CFR 50.36, Technical specifications (TSs), when deleting TS limiting conditions for operation and adding surveillance requirements.
The licensee needs to clearly define dose equivalent iodine-131 in the FitzPatrick TSs so that the definition remains applicable to all design-basis accidents that utilize iodine dose conversion factors. The licensee should consider changing the dose conversion factor terminology from total effective dose equivalent to committed effective dose equivalent for the loss of coolant and fuel handling accidents, in addition to accounting for the different iodine dose conversation factors used in the different design-basis accidents.
In the licensees presentation, two items are shown to be inserted into primary containment leakage rate testing program in the TSs. These items state an exemption from a specific portion of 10 CFR Part 50, Appendix J, will be taken. It was not clear to the NRC staff if an exemption request was going to be part of the submittal. Therefore, the NRC staff provided feedback that the term exemption has specific regulatory meaning, and that if it is the licensees intention to request an exemption, the licensee should provide the exemption request with the necessary information and ensure the correct regulatory processes are used. In addition, if an exemption request is submitted, it should be accounted for in the licensees requested review time schedule.
The licensee needs to address the seismic adequacy of mechanical and electrical equipment as the basis for negating the seismic qualification requirements for systems, structures, and components (such as main steam isolation valves leakage bypass piping and other piping systems, electrical equipment, heating, ventilation, and air condition system components (including the control room and auxiliary electrical equipment room, etc.)), credited in an AST LAR.
The licensee is required to show that all systems, structures, and components credited for AST shall be structurally capable of remaining functional during and following a safe shutdown earthquake.
The schedule currently calls for the LAR to be submitted in July 2019. This is a change from the schedule noted in the licensees slides.
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 20, 2019, MEETING WITH EXELON GENERATION COMPANY, LLC PLANNED LICENSE AMENDMENT REQUEST REGARDING MAIN STEAM ISOLATION VALVE LEAK RATE INCREASE UTILIZING ALTERNATE SOURCE TERM ANALYSIS NRC Participants Carleen Parker John Parillo Kevin Hsueh Dan Hoang Gush Singh Carolyn Fairbanks Dan Barnhurst Jason White Matt Yoder Nageswara Karipineni Donna Williams Jorge Cintron-Rivera Sheila Ray Michael Breach Josh Borromeo Kevin Quinlan Kristy Bucholtz Muhammad Razzaque James Danna Exelon Participants Shane Gardner John Massari Ron Reynolds Bill Drews Katherine Leaveck Enclosure
ML19183A128 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
