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Category:Meeting Summary
MONTHYEARML24214A1402024-08-0505 August 2024
July 24, 2024, Summary of the Public Meeting Regarding Clinton Power Station, Unit 1, Partial Site Release
ML24183A1642024-07-0202 July 2024
June 27, 2024, Summary of the Public Outreach to Discuss the NRC 2023 End-Of-Cycle Plant Performance Assessment of Clinton Power Station, Unit 1
ML24135A3722024-05-22022 May 2024
Enclosure 1 - Meeting Summary for May 7 and May 9 2024 Public Scoping Meetings
ML24128A2512024-05-14014 May 2024
Summary of April 11, 2024, Public Meeting with Constellation Energy Generation, LLC Regarding Proposed Alternative to Implement American Society of Mechanical Engineers Operation and Maintenance Code Case OMN-32
ML24113A2872024-04-25025 April 2024
Summary of Public Meeting with Constellation Energy Generation, LLC Regarding Hooded Masks
ML24032A0862024-02-0202 February 2024
Summary of Meeting with Constellation Energy Generation, LLC, on Planned Requests to Use Code Case N-932
ML23320A2472023-11-17017 November 2023
Constellation - Summary of November 14, 2023, Public Pre-Application Meeting with Constellation Energy Generation, LLC on Adoption of TSTF-591
ML23263B1062023-09-22022 September 2023
R. E. Ginna Nuclear Power Plant - Constellation - Pre-Application Amse 9/18/2023 Meeting Summary
ML23198A0152023-07-27027 July 2023
License Renewal Application Public Meeting Summary of Pre-Submittal Meeting
ML23200A2592023-07-24024 July 2023
June 27, 2023, Clinton Power Station License Renewal Environmental Pre-application Public Meeting-Meeting Summary
ML23173A0142023-06-22022 June 2023
Summary of the June 14, 2023, Public Outreach to Discuss the NRC 2022 End-of-Cycle Plant Performance Assessment of Clinton Power Station, Unit 1
ML23055A0352023-03-24024 March 2023
Summary of February 23, 2023, with Constellation Energy Generation, LLC on Proposed Changes to Emergency Plans to Revise Emergency Action Levels
ML22140A2912022-05-23023 May 2022
Summary of Public Outreach to Discuss the NRC 2021 End-Of-Cycle Plant Performance Assessment of Clinton, Unit 1, and Lasalle, Units 1 and 2
ML22032A3112022-02-18018 February 2022
January 31, 2022, Summary of Presubmittal Meeting Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC, Extending the Clinton Power Station, Unit 1, Secondary Containment to Include the Fuel Building Railroad Ai
ML21333A1532021-11-30030 November 2021
Summary of November 16, 2021, Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Alternative to Extend the Inservice Inspection Interval
ML21237A0412021-08-30030 August 2021
Summary of the July 27, 2021, Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Use Case OMN-28,
ML21195A3932021-07-14014 July 2021
June 30, 2021, Summary of Public Outreach to Discuss the NRC 2020 End-Of-Cycle Plant Performance Assessment of Clinton Power Station, Unit 1, and Lasalle County Station, Units 1 & 2
ML21176A0822021-07-0606 July 2021
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
ML21139A1852021-06-22022 June 2021
Summary of Meeting with Exelon Generation Company, LLC Regarding Its Requested Alternative to Eliminate Certain Documentation Requirements for the Replacement of Pressure Retaining Bolting
ML21028A1472021-01-28028 January 2021
Summary of January 21, 2021, Presubmittal Meeting Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Regarding One-Time Extension of the Clinton Power Station, Unit 1, Containment Type a ILRT Frequency EPID L-
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
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)
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
ML20239A8252020-08-25025 August 2020
Summary of the August 4, 2020 Public Webinar to Discuss the NRC 2019 End-Of-Cycle Plant Performance Assessment of Clinton Power Station, Unit 1
ML20181A0002020-06-29029 June 2020
Summary of 6/24/20 Meeting with Exelon Generation Company, LLC Regarding Planned Request for Alternative to Supplemental Valve Position Indication Testing Requirements for Braidwood, Calvert Cliffs, Clinton, Limerick, Nine Mile, Peach Botto
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
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
ML19162A0272019-06-21021 June 2019
Summary of June 4, 2019, Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Extend the Test Interval for Safety Relief Valves
ML19036A8832019-02-0707 February 2019
Summary of Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Use ASME Code Case N-879
ML18354B1712019-01-0202 January 2019
Summary of December 19, 2018, Meeting with Exelon Generation Company, LLC Regarding the Use of Boiling Water Reactor Vessel and Internals Project Guidelines
IR 05000461/20180512018-12-19019 December 2018
Summary of November 30, 2018, Meeting with Exelon Generation Company, LLC Regarding the Preliminary Safety Significance Determination in NRC Inspection Report 05000461/2018051 Dated November 6, 2018
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
ML18297A1722018-10-26026 October 2018
Summary of Meeting with Exelon Generation Company, LLC Regarding Planned License Amendment Request to Adopt TSTF-427
ML18120A1772018-05-0101 May 2018
Summary of Meeting with Exelon Generation Company, LLC Regarding Draft Guidance for Emergency Response Organization Staffing
ML18099A2562018-04-0909 April 2018
March 28, 2018, Summary of the Public Outreach/Open House to Discuss the NRC 2017 End-of-Cycle Plant Performance Assessment of Clinton Power Station
ML18065A8362018-03-0707 March 2018
Summary of February 27, 2018, Meeting with Exelon Generation Company, LLC Planned Fleet License Amendment Request to Relocate Staff Qualification Requirements from TSs to the Quality Assurance Topical Report
ML18058A5232018-03-0101 March 2018
Summary of February 26, 2018, Meeting with Exelon Generation Company, LLC Regarding Proposed Alternative to the Main Steam Isolation Valve Testing Requirements
ML17347B1022017-12-14014 December 2017
Summary of Meeting with Exelon Generation Company, LLC on Its Planned Fleet License Amendment Request to Revise the Minimum Staffing Requirements for Emergency Response
ML17184A0092017-07-10010 July 2017
Summary of June 29, 2017, Meeting with Exelon Generation Company, LLC, on Proposed Changes to Emergency Plans to Revise Emergency Action Levels (CAC Nos. MF9779-MF9801)
ML17096A6512017-04-0606 April 2017
Summary of Public Outreach/Open House to Discuss the NRC 2016 End-Of-Cycle Plant Performance Assessment of Clinton Power Station
ML17067A3722017-03-16016 March 2017
March 7, 2017, Summary of Public Pre-Submittal Teleconference Meeting with Exelon Generation Company, LLC to Discuss Proposed License Amendment Request Regarding Residual Heat Removal System Operability in Mode 3 at Clinton Power Station, U
ML16307A3162016-11-28028 November 2016
Summary of Public Meeting with Exelon to Discuss Pre-Submittal License Amendment Requests And/Or Exemptions to Part 37 for Decommissioning Plans for Clinton, Quad Cities, and Oyster Creek
ML16195A4482016-07-22022 July 2016
Summary of July 12, 2016, Public Meeting with Exelon to Discuss Decommissioning Transition Plans for Clinton, Quad Cities, and Oyster Creek
ML16085A3292016-04-0606 April 2016
Summary of March 22, 2016, Meeting with Exelon Generation Company, LLC, on Proposed License Amendment Request to Adopt ANSI 3.1-2014 Operating Training Standards
ML16095A3072016-04-0101 April 2016
Summary of the March 30, 2016, Public Outreach/Open House to Discuss the NRC 2015 End-Of-cycle Plant Performance Assessment of Clinton Power Station
ML16040A2182016-02-11011 February 2016
January 21, 2016, Summary of Meeting with Exelon Generation Company, LLC Licensing Managers
ML16035A1762016-02-11011 February 2016
Summary of January 7, 2016, Meeting with Exelon Generation Company, LLC on It'S Planned Fleet License Amendment Request to Revise the Minimum Staffing Requirements for Emergency Response (CAC Nos. MF7162 - MF7183)
ML16032A4112016-02-0404 February 2016
Summary of December 9, 2015 Meeting with Exelon Generation Company, LLC to Discuss Proposed Submittal Related to Secondary Containment Airlock Extension
ML15072A4242015-04-16016 April 2015
February 23, 2015, Summary of Meeting with Exelon Generation Company, LLC Regarding Relief Request for Clinton Power Station, Unit 1 (TAC Nos. MF5334, MF5344, and MF5345
2024-08-05
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 June 23, 2009 LICENSEE:
Exelon Generation Company, LLC. FACILITY:
Clinton Power Station, Unit NO.1 SUB..IECT:
SUMMARY
OF JUNE 2, 2009, CONFERENCE CALL WITH EXELON GENERATION COMPANY, LLC, ON THE COBALT ISOTOPE GENERATION PROJECT On June 2, 2009, the U.S. Nuclear Regulatory Commission (NRC) and representatives of Exelon Generation Company, LLC (EGC), held a conference call to give the licensee the opportunity to clarify the guidance provided by the NRC staff in its May 19, 2009, withdrawal acknowledgement letter (See the enclosure to Agencywide Documents Access and Management System (ADAMS) Accession No. ML091280171).
A list of call participants is provided in the Enclosure.
Background By letter dated April 8,2009, (ADAMS Accession No. ML090990454), EGC submitted a license amendment request for Clinton Power Station (CPS), Unit NO.1 that would revise the CPS operating license and technical specifications to allow the intentional production of the isotope Cobalt (Co)-60 from Co-59 targets inserted into the reactor. By letter dated May 11, 2009, (ADAMS Accession No. ML091320432), Exelon requested the withdrawal of the application from the NRC staffs review. The NRC staff was in the process of completing its acceptance review when it received the licensee's request for withdrawal.
The NRC staff noted in its withdrawal acknowledgement letter that its review identified areas where the application did not provide sufficient technical information to enable the staff to complete its detailed review. The letter included guidance to aid the licensee should they decide to resubmit the application.
Summary Following introductions, EGC staff updated the call participants on the actions the licensee had taken since the withdrawal letter was submitted.
The licensee informed the NRC staff that the technical evaluations needed to support a follow-up amendment were complete and the results were being incorporated into a new submittal.
The licensee expects to send in the new submittal on or about June 26, 2009. During the discussion of the current status of the project, the licensee and the NRC staff clarified several of the information items listed in the enclosure to the June 2, 2009, letter. The NRC staff also asked several questions about the pending licensing action, including to what extent were evaluations made under Title 10 of the Code of Federal Regulations (10 CFR), Section 50.59, included as part of the project. The licensee responded that the scope of the amendment will cover most aspects of the project, with the exception of those portions not normally covered by the amendment process (e.g., procedure development).
When questioned, the licensee also indicated that they plan to use an approved cask design to store and transport the byproduct material.
-2 The licensee also indicated that they have alternative plans in place in the event the NRC staff does not accept the application, denies the application, or cannot complete the evaluation before the date when new fuel assemblies must be ordered, which is estimated to be August 20, 2009. In these instances, the license would order the production of new fuel assemblies to take the place of the assemblies containing the Co-59 targets. The NRC staff further clarified the L1C-109, "Acceptance Review Procedures," process is performed to ensure the application contains the technical information necessary for the NRC staff to perform its detailed review, but is not a determination of the application's acceptability.
The licensee should not make any decisions about producing or not producing replacement fuel assemblies based on the results of the NRC acceptance review of the application.
The NRC staff also clarified that the project would not involve a new license under 10 CFR Part 30, "Rules of General Applicability to Domestic Licensing of Byproduct Material," to produce byproduct material, but noted that the licensee must fully describe in accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," the changes planned for the operating license that would be necessary to authorize activities anticipated under this project. The NRC emphasized with the licensee that, due to the short time allotted for review, the application needs to be complete and of very high quality as to minimize unnecessary questions between the staffs. The NRC staff also reminded the licensee that the responses to any request for additional information should be responded to expeditiously.
The licensee stated that the General Electric Hitachi (GEH) Safety Analysis Report (SAR), Revision 0, will be complete and available to the NRC staff for audit by the time the application is ready for submittal, but that the Cycle 13 reload analysis and the GEH SAR Revision 1, which evaluates the impact of Co-60 production on the Cycle 13 core physics, in-core signals, and accident analyses, will not be completed until November 2009. The licensee took an action to verify that the calculations necessary to support the application would be available for NRC review in the Washington D.C. area. Questions regarding this call should be referred to Christopher Gratton at 301-415-1055, or Christopher.Gratton@nrc.gov.
Christopher Gratton, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.
List of cc w/encl: Distribution via LIST OF A JUNE 2,2009, MEETING WITH EXELON GENERATION COMPANY, CO-50 GENERATION Office of Nuclear Reactor Regulation (NRR) Christopher Gratton, DORL Stephen Sands, DORL Paul Clifford, DSS Aleem Boatright, DRA Steven Garry, DIRS Methew Panicker, DSS Anthony Mendiola, DSS Mark Blumberg, DRA Office of Federal and State Materials and Environmental Management Programs (FSME) Donna-Beth Howe, MSSA Exelon Generation Company, LLC (EGC) Mike Reitmeyer Jeff Hansen Tim Byam Doug Wise Chris Monetta Brad Bloomquist Lisa Schichlein Jim Harrison Mike Downs Enclosure
-2 The licensee also indicated that they have alternative plans in place in the event the NRC staff does not accept the application, denies the application, or cannot complete the evaluation before the date when new fuel assemblies must be ordered, which is estimated to be August 20, 2009. In these instances, the license would order the production of new fuel assemblies to take the place of the assemblies containing the Co-59 targets. The NRC staff further clarified the L1C-109, "Acceptance Review Procedures," process is performed to ensure the application contains the technical information necessary for the NRC staff to perform its detailed review, but is not a determination of the application's acceptability.
The licensee should not make any decisions about producing or not producing replacement fuel assemblies based on the results of the NRC acceptance review of the application.
The NRC staff also clarified that the project would not involve a new license under 10 CFR Part 30, "Rules of General Applicability to Domestic Licensing of Byproduct Material," to produce byproduct material, but noted that the licensee must fully describe in accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," the changes planned for the operating license that would be necessary to authorize activities anticipated under this project. The NRC emphasized with the licensee that, due to the short time allotted for review, the application needs to be complete and of very high quality as to minimize unnecessary questions between the staffs. The NRC staff also reminded the licensee that the responses to any request for additional information should be responded to expeditiously.
The licensee stated that the General Electric Hitachi (GEH) Safety Analysis Report (SAR), Revision 0, will be complete and available to the NRC staff for audit by the time the application is ready for submittal, but that the Cycle 13 reload analysis and the GEH SAR Revision 1, which evaluates the impact of Co-60 production on the Cycle 13 core physics, in-core signals, and accident analyses, will not be completed until November 2009. The licensee took an action to verify that the calculations necessary to support the application would be available for NRC review in the Washington D.C. area. Questions regarding this call should be referred to Christopher Gratton at 301-415-1055, or Christopher.Gratton@nrc.gov.
IRA! Christopher Gratton, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.
List of cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsOgcRp Resource ABoatright.
NRR Branch Reading LPL3-2 RidsRgn3MailCenter Resource MPanicker, NRR RidsAcrsAcnw_MailCTR Resource CTucci, NRR AMendiola, NRR RidsNrrDorlLpl3-2 Resource DHowe, FSME MBlumberg, NRR RidsNrrPMClinton Resource PClifford, NRR SBagley, EDO Region 3 RidsNrrLATHarris Resource SGarry, NRR ADAMS Accession No ML091671123 OFFICE DORULPL3-2IPM DORULPL3-2ILA DORULPL3-2IBC DORULPL3-2IPM NAME CGratton THarris SCampbell CGratton DATE 06123109 06123109 06123109 06123109 OFFICIAL RECORD COpy
