Letter Sequence Meeting |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement
Administration
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
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MONTHYEARML0515100172005-05-31031 May 2005 Draft RAI on Response to Generic Letter 2004-02 Project stage: Draft RAI ML0515303042005-06-0303 June 2005 6/3/05, Calvert Cliffs - RAI Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors Project stage: RAI ML0603803582006-02-0909 February 2006 RAI, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML0609500512006-04-12012 April 2006 Approval of Extension Request for Completion of Corrective Actions in Response to Generic Letter 2004-02 Project stage: Other ML0618702222006-06-30030 June 2006 Calvert Cliffs, Units 1 & 2 Update of Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Basis Accidents at Pressurized Water Reactors Project stage: Other ML0626405472006-09-20020 September 2006 Update of Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML0633407022006-12-18018 December 2006 Unit No.1 - Approval of Extension Request for Completion of Corrective Action in Response to Generic Letter 2004-02 Project stage: Other ML0712703722007-05-0202 May 2007 Calvert Cliffs Revision to Generic Letter 2004-02 Response Project stage: Other ML0734504992007-12-10010 December 2007 Attachment (1) Request for Extension of the Completion Date for Corrective Actions Related to Generic Letter 2004-02 Project stage: Request ML0734504982007-12-10010 December 2007 Request for Extension for Completion of Activities Related to Generic Letter 2004-02 Project stage: Request ML0811307392008-04-22022 April 2008 Revision to Generic Letter 2004-02 Response Project stage: Other ML0817101052008-06-18018 June 2008 Attachment 1, Request for Extension of the Completion Date for Corrective Actions Related to Generic Letter 2004-02 Project stage: Request ML0827404892008-09-30030 September 2008 Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors. Project stage: Supplement ML0827404972008-09-30030 September 2008 Calvert Cliffs Nuclear Plant, Attachment 2, ECCS and CS System Figures Project stage: Other ML0833003202008-12-0404 December 2008 Request for Additional Information Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors-Calvert Cliffs Unit 1 & 2 Project stage: RAI ML0906807672009-03-0404 March 2009 Request for Additional Information: Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Supplement ML1009500782010-04-12012 April 2010 Request for Additional Information Generic Letter 2004-02 Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2-(TAC Nos. MC4672 and MC4673) Project stage: RAI ML1011903842010-05-0606 May 2010 Notice of Forthcoming Conference Call with Calvert Cliffs to Discuss Supplemental Responses to Generic Ltr. 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Request ML1014708982010-06-0707 June 2010 Summary of Meeting with Calvert Cliffs Nuclear Power Plant, LLC, to Discuss Supplement to Responses to Generic Letter 2004-02 Project stage: Meeting ML1028701002010-09-30030 September 2010 Catawba Units 1 & 2, Draft Responses to NRC Request for Additional Information Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents on Pressurized-Water.... Project stage: Request ML1029306502010-10-20020 October 2010 Notice of Forthcoming Conference Call with Duke Energy Carolinas, LLC Regarding McGuire Nuclear Station, Units 1 and 2 and Catawba Nuclear Station, Units 1 and 2, Project stage: Other ML1031903612010-11-10010 November 2010 Response to Request for Additional Information Regarding Generic Letter 2004-02 (TAC Nos. MC4672 and MC4673) Project stage: Response to RAI ML1030810242010-11-10010 November 2010 Summary of November 1, 2010, Meeting with Duke to Discuss Responses to Generic Letter (GL) 2004-02 (Tac Nos. MC4673, MC4674, MC4692, and MC4693) Project stage: Meeting ML13086A5512013-01-24024 January 2013 MC4672 & MC4673 - CCNPP-CHLE-003, Rev 0c Chemical Effects Pirt Considerations Excerpts with Respect to GL2004-02, GSI-191 Project stage: Other ML13038A5432013-01-24024 January 2013 Chemical Effects Head Loss Experiment (Chle) Test Protocol for Calvert Cliffs Nuclear Power Plant (CCNPP-CHLE-002, Revision 0d) Project stage: Request ML13050A5112013-02-19019 February 2013 MC4672-3 Corrected Notice -Public Meeting on March 20, 2013 Re-GL2004-02 Project stage: Request ML13045A1822013-02-19019 February 2013 March 20, 2013, Notice of Forthcoming Teleconference with Calvert Cliffs and Nrc/Nrr Staff to Have Additional Discussions of Licensees'S Proposed Path for Resolution of Generic Letter 2004-02 Project stage: Meeting ML13086A5502013-03-0101 March 2013 MC4672 & MC4673, CCNPP-CHLE-002, Rev 0e Chemical Effects Experimental Protocol with Respect to GL2004-02, GSI-191. Project stage: Request ML13088A2202013-03-18018 March 2013 MC4672 & MC4673 - CCNPP-CHLE-005, Rev 1 Chemical Effects Autoclave Experimental Plan with Respect to GL2004-02, GSI-1 91 Project stage: Request ML13086A5492013-03-20020 March 2013 MC4672 & MC4673 - Licensee Presentation-Category 1, Public Meeting on March 20, 2013 with Respect to GL2004-02, GSI-191 Project stage: Meeting ML13091A0552013-04-10010 April 2013 Summary of Meeting on March 20, 2013, with Calvert Cliffs Nuclear Power Plant, LLC, to Discuss the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation D Project stage: Meeting ML13149A3992013-05-20020 May 2013 Chemical Effects Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-005, Revision 2, May 20, 2013 Project stage: Request ML13149A3942013-05-20020 May 2013 Chemical Effects Head Loss Experiment (Chle) Test Protocol for Calvert Cliffs Nuclear Power Plant, CCNPP-CHLE-002, Revision 0 May 20, 2013 Project stage: Request ML13149A4052013-05-23023 May 2013 Metals BENCH-TOP Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant, CCNPP-CHLE-006, Revision 0, May 23, 2013 Project stage: Request ML13148A3962013-05-29029 May 2013 Forthcoming Meeting with Calvert Cliffs Nuclear Power Plant, LLC to Discuss Licensee'S Proposed Plan for Resolution of GL 2004-02 Project stage: Meeting ML13179A3132013-07-11011 July 2013 June 12, 2013 Summary of Meeting with Constellation Energy Group, Inc., to Continue Discussions on the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculati Project stage: Meeting ML13224A0942013-08-0606 August 2013 Chemical Effects Pirt Considerations for Calvert Cliffs Nuclear Power Plant, CCNPP-CHLE-003, Revision 0c Project stage: Request ML13224A1032013-08-0808 August 2013 CCNPP-CHLE-007, Revision 0c, Coatings Bench-Top Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant. Project stage: Request ML13226A0902013-08-14014 August 2013 Notice of Forthcoming Meeting with Constellation Energy Nuclear Group, LLC Project stage: Meeting ML13304B4032013-11-0101 November 2013 Notice of Forthcoming Meeting with Constellation Energy Nuclear Group, LLC, Project stage: Meeting ML13319A9392013-11-13013 November 2013 Ri GSI-191 November 2013 Meeting with NRC Rev 0 Project stage: Request ML13310B9292013-12-0606 December 2013 Summary of Meeting with Constellation Energy Group, Inc., to Continue Discussions on the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During ... Project stage: Meeting ML14014A0392014-01-29029 January 2014 Summary of Meeting with Constellation Energy Group, Inc., to Continue Discussions on the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During.. Project stage: Meeting ML14206B0012014-02-14014 February 2014 Long-Term Chemical Effects Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant. CCNP-CHLE-011, Revision 2 Project stage: Request ML14142A3232014-05-22022 May 2014 NRR E-mail Capture - Calvert Cliffs May 21, 2014 Public Meeting Presentation Project stage: Request ML14206A9932014-07-25025 July 2014 Conrete Bench-Top Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant. CCNPP-CHLE-010, Revision 1 Project stage: Request ML14206B1442014-11-0606 November 2014 May 21, 2014 Summary of Meeting with Exelon Generation Company, LLC, to Continue Discussions on the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02 Project stage: Meeting ML14206A2062014-11-0707 November 2014 July 2, 2014 Summary of Meeting with Exelon Generation Company, LLC to Continue Discussions on the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02 Project stage: Meeting RS-15-091, Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2015-03-31031 March 2015 Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink Project stage: Response to RAI ML15154B5572015-06-17017 June 2015 May 19, 2015 Summary of Meeting with Exelon Generation Company, LLC, on Calvert Cliffs Nuclear Power Plant, Units 1 and 2 - Chemical Effects Testing for Resolution of Generic Letter 2004-02 (TAC Nos. MC4672 & MC4673) Project stage: Meeting 2013-11-01
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Category:Meeting Briefing Package/Handouts
MONTHYEARML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML23033A6662023-02-0909 February 2023 Summary of Public Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Its Request for Alternatives for Certain Steam Generator Weld Inspections for Calvert Cliffs 1 & 2, Byron 1 & 2, Braidwood 1 & 2, and Ginna ML23033A6672023-01-30030 January 2023 Public Call with Constellation January 30, 2023 (Slides) ML22013A3942022-01-13013 January 2022 Presentation Information for Pre-Submittal Meeting Regarding Relief Request to Use the Carbon Fiber Reinforced Polymer (Cfrp) Composite System ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) ML21144A0172021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request Pre-Submittal Meeting ML21134A0162021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request - NRC Pre-submittal Meeting Telecon May 24, 2021 (EPID L-2021-LRM-0051) (Slides) ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20246G8772020-09-0303 September 2020 Licensee'S Presentation for September 3, 2020 Public Telephone Conference ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20168A3192020-06-15015 June 2020 Joint Annual Assessment Meeting for Pa/Md Power Plants - Webinar Presentation ML19318F9512019-11-20020 November 2019 Presentation Slides for November 20, 2019, Pre-Application Meeting - Request for Revision to Quality Assurance Program Internal Audit Frequency ML19317C9952019-11-12012 November 2019 In-Service Testing Supplemental Position Indication Relief Request NRC Pre-Application Meeting November 18, 2019 ML19246B7162019-08-29029 August 2019 Meeting Between NRC and Exelon Regarding Calvert Cliffs-2 LAR to Use Framatome ATF LTAs ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19151A6602019-05-31031 May 2019 BWR Fleet Mssv/Srv Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19022A2002019-01-23023 January 2019 Request for Use of ASME Code Case N-879 for Exelon Nuclear Power Plants ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18276A0712018-10-0404 October 2018 Exelon'S Presentation for October 4, 2018 Public Pre-Submittal Meeting on Planned Calvert Cliffs 10CFR50.69 LAR ML18171A0842018-06-21021 June 2018 GSI-191 Program Use of Risk Metrics for Containment Sump Tech Spec Operability Determination June 21, 2018 Public Meeting Slides (MF8521, MF8522; L-2016-LRM-0001) ML18190A3922018-06-14014 June 2018 Licensee Presentation Material for June 14, 2018 Public Meeting ML18136A4932018-05-16016 May 2018 Licensee'S Slides for Pre-Application Meeting W/Exelon Re Planned GSI-191 LAR for Calvert Cliffs (L-2016-LRM-0001) ML18096A0222018-04-0404 April 2018 Annual Assessment Meeting 04/04/2018 Handouts ML18096A9902018-03-12012 March 2018 NRC Pre-Submittal Call Briefing Notes, Calvert Cliffs Emergency Planning Future Licensing Actions ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML17142A2382017-05-25025 May 2017 OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns ML17143A1612017-05-23023 May 2017 Annual Assessment Meeting Handout and Sign in Sheet ML16274A0012016-09-30030 September 2016 PWR MSIP Analysis and Measurements ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16075A3292016-03-16016 March 2016 OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations ML15321A3702015-12-0101 December 2015 GSI-191 Program Strainer Head Loss Testing and Option 2b Closure Approach ML15308A1072015-11-0505 November 2015 TSTF-505 LAR - NRC Pre-Submittal, November 5, 2015 Meeting Slides ML15282A0832015-10-0808 October 2015 October 8, 2015, Public Meeting Regarding the NFPA-805 License Amendment Application - Final ML15279A4992015-10-0808 October 2015 October 8, 2015, Public Meeting Regarding the NFPA-805 License Amendment Application ML15222A5472015-08-31031 August 2015 GSI 191 Program Chemical Effects Testing Update Option 2b Closure Approach ML15152A0822015-06-0404 June 2015 Presentation for the June 4, 2015 Public Meeting Regarding the National Fire Protection Association Standard 805 License Amendment Request ML14230A9132014-08-18018 August 2014 Enclosure - Fuel Performance and Cask Internals - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L ML14230A9112014-08-18018 August 2014 Enclosure - Example AMP - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 ML14230A9102014-08-18018 August 2014 Enclosure - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 2024-01-30
[Table view] Category:Meeting Summary
MONTHYEARML23352A0592024-01-0909 January 2024 Summary of December 11, 2023, Meeting with Constellation on Alternative Request Involving Carbon Fiber Reinforced Polymer Composite 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 ML23179A0012023-06-28028 June 2023 6/7/2023 - Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - Meeting Summary 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 ML23033A6662023-02-0909 February 2023 Summary of Public Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Its Request for Alternatives for Certain Steam Generator Weld Inspections for Calvert Cliffs 1 & 2, Byron 1 & 2, Braidwood 1 & 2, and Ginna ML22264A1992022-11-14014 November 2022 Summary of August 22, 2022, Meeting Between the U.S. Nuclear Regulatory Commission and Constellation Energy Generation, LLC, Regarding Performance Monitoring of Steam Generator Welds (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and ML22187A1462022-07-0606 July 2022 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Meeting Summary ML22159A2272022-06-0808 June 2022 Summary of May 10, 2022, Pre-Application Meeting Between the U.S. Nuclear Regulatory Commission and Constellation Energy Generation, Llc, Regarding a Proposed License Amendament Request (Lar) for Calvert Cliffs Nuclear Power Plant ML22144A0202022-05-26026 May 2022 Summary of Meeting Between the U.S. Nuclear Regulatory Commission and Constellation Energy Generation, LLC, Regarding Proposed Alternative for Examinations of Certain Pressurizer Welds at Calvert Cliffs ML22066A0012022-03-22022 March 2022 Summary, January 10, 2022, Closed Meeting with Exelon Generation Company, Llc, Proposed Relief Request for Alternative Repair of Buried Saltwater Piping with Carbon Fiber Reinforced Polymer Composite System 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, ML21228A0742021-08-27027 August 2021 Summary of July 13, 2021, Meeting with Exelon Generation Company, LLC Concerning License Amendment Request for Calvert Cliffs Nuclear Power Plant, Units 1 and 2, Concerning Spent Fuel Pool Cooling Design Basis Change (L-2021-LLA-0112) 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 ML21161A1082021-06-25025 June 2021 Summary of Pre-Application Meeting with Exelon Generation Company, LLC on Planned Submittal of License Amendment Request for Calvert Cliffs Nuclear Power Plant, Units 1 and 2, Concerning Spent Fuel Pool Cooling Design Basis Change 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 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 ML20272A0132020-10-0707 October 2020 Summary of September 3, 2020, Meeting with Exelon Generation Company, LLC Concerning Supplemental Position Indication Testing Interval Alternative Request ML20197A2722020-07-15015 July 2020 2020 Beaver Valley, Calvert Cliffs, Limerick Peach Bottom, Susquehanna Annual Assessment Webinar Summary 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 ML19136A2752019-05-15015 May 2019 Aam 2019 Meeting Summary ML19135A1052019-05-15015 May 2019 Aam Summary Data Sheet of 2018 Plant Performance ML20108F0902019-04-20020 April 2019 April 15, 2020, Meeting Summary with Exelon Generation Company, LLC Regarding Planned Request to Defer Submittal of Owner'S Activity Report (Braidwood 2,Byron 2,Calvert Cliffs 1, LaSalle 1, Limerick 1, Nine Mile Point 2, Quad 2, R. E. Ginna 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 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 ML18292A8202018-10-24024 October 2018 October 4, 2018, Summary of Pre-Application Meeting with Exelon Generation Co., LLC on Planned Submittal of Licensing Action for Calvert Cliffs Nuclear Power Plant, Units 1 and 2, Risk-Informed Categorization and Treatment ML18197A2292018-07-20020 July 2018 Summary of Meeting with Exelon Generation Company, Llc, on Planned Submittal of Risk Informed License Amendment and Exemption Requests Concerning Resolution of Generic Issue 191 (CAC Nos. MF8521 and MF8522; EPID L-2016-LRM-0001) ML18197A4362018-07-18018 July 2018 May 21, 2018, Summary of Meeting with Exelon Generation Company, LLC, on Planned Submittal of Risk-Informed License Amendment and Exemption Requests Concerning Resolution of Generic Issue 191 ML18191A9962018-07-13013 July 2018 Plants, - Summary of June 14, 2018, Meeting with Exelon Generation Company, LLC, on Planned Submittal of License Amendments Concerning Alternating Current Sources and Control Room Emergency Ventilation System ... ML18120A1772018-05-0101 May 2018 Summary of Meeting with Exelon Generation Company, LLC Regarding Draft Guidance for Emergency Response Organization Staffing ML18096B0782018-04-12012 April 2018 Summary of Meeting with Exelon Generation Company, LLC, on Planned Submittal of License Amendments Concerning Emergency Operation Facility and Technical Support Center (EPID L-20118-LRM-0016) ML18096B1982018-04-0606 April 2018 Summary of Public Annual Assessment Meeting Calvert Cliffs Nuclear Power Plant Dated April 6, 2018 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 ML17249A3202017-09-18018 September 2017 Summary of Meeting with Exelon Generation Company, LLC, on Planned Submittal of Risk-Informed License Amendment and Exemption Requests Concerning Resolution of Generic Issue 191 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) ML17143A3572017-05-23023 May 2017 Summary of Public Meeting Calvert Cliffs Nuclear Plant ML16228A0622016-08-15015 August 2016 Summary of July 26, 2016, Public Meeting on Status of Associated Effects Submittals Related to the Reevaluated Flood Hazards at Exelon Generation Company, LLC Sites as Part of the Response to Near-Term Task Force Recommendation 2.1, Floodin ML16118A1322016-04-26026 April 2016 4/21/2016 - Summary of Annual Assessment Meeting for Calvert Cliffs Nuclear Power Plant ML16117A1972016-04-21021 April 2016 4/21/2016 - Calvert Cliffs Nuclear Power Plant, Units 1 and 2, Annual Assessment Meeting, and Sign-in Sheet and Summary Data Sheet ML16075A4562016-04-12012 April 2016 February 24, 2016, Summary of Meeting with Exelon Generation Company, LLC, to Discuss the Flaw Indication in the Calvert Cliffs Unit 1 Pressurizer Safety Valve Dissimilar Metal Weld 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 2024-01-09
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides NEI 99-01, Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides2023-02-21021 February 2023 Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides ML23033A6662023-02-0909 February 2023 Summary of Public Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Its Request for Alternatives for Certain Steam Generator Weld Inspections for Calvert Cliffs 1 & 2, Byron 1 & 2, Braidwood 1 & 2, and Ginna ML23033A6672023-01-30030 January 2023 Public Call with Constellation January 30, 2023 (Slides) ML22124A1492022-05-10010 May 2022 (Ccnpp) Control Element Assembly (CEA) Recovery Time Improvement Project LAR Pre-Submittal Non-Proprietary (Public) ML22124A1482022-05-10010 May 2022 (Ccnpp) Control Element Assembly (CEA) Recovery Time Improvement Project LAR Pre-Submittal Redacted (Public) ML22013A3942022-01-13013 January 2022 Presentation Information for Pre-Submittal Meeting Regarding Relief Request to Use the Carbon Fiber Reinforced Polymer (Cfrp) Composite System ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) ML21162A3322021-06-11011 June 2021 BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs ML21144A0172021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request Pre-Submittal Meeting ML21134A0162021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request - NRC Pre-submittal Meeting Telecon May 24, 2021 (EPID L-2021-LRM-0051) (Slides) ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20246G8772020-09-0303 September 2020 Licensee'S Presentation for September 3, 2020 Public Telephone Conference ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20163A6542020-06-18018 June 2020 2020 NRC Annual Assessment Webinar Presentation - Pennsylvania and Maryland Facilities (Beaver Valley, Calvert Cliffs, Limerick, Peach Bottom, Susquehanna) ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20168A3192020-06-15015 June 2020 Joint Annual Assessment Meeting for Pa/Md Power Plants - Webinar Presentation ML19246B7162019-08-29029 August 2019 Meeting Between NRC and Exelon Regarding Calvert Cliffs-2 LAR to Use Framatome ATF LTAs ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18276A0712018-10-0404 October 2018 Exelon'S Presentation for October 4, 2018 Public Pre-Submittal Meeting on Planned Calvert Cliffs 10CFR50.69 LAR ML18171A0842018-06-21021 June 2018 GSI-191 Program Use of Risk Metrics for Containment Sump Tech Spec Operability Determination June 21, 2018 Public Meeting Slides (MF8521, MF8522; L-2016-LRM-0001) ML18136A4932018-05-16016 May 2018 Licensee'S Slides for Pre-Application Meeting W/Exelon Re Planned GSI-191 LAR for Calvert Cliffs (L-2016-LRM-0001) ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML16328A2832016-11-18018 November 2016 Supplemental Presentation Slides for 10/25/2016 Public Meeting Via E-mail from K.Greene to R.Guzman Calvert Cliffs GSI-191 Resolution Update ML16307A4902016-10-25025 October 2016 Presentation Slides from Public Meeting Calvert Cliffs GSI-191 Resolution Update ML16274A0012016-09-30030 September 2016 PWR MSIP Analysis and Measurements ML16242A1782016-09-0101 September 2016 Presentation Slides from Public Meeting Regarding Calvert Cliffs GSI-191 Resolution Update ML16198A0012016-07-18018 July 2016 Presentation Slides from Public Meeting Regarding Calvert Cliffs GSI-191 Resolution Update ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML15321A3702015-12-0101 December 2015 GSI-191 Program Strainer Head Loss Testing and Option 2b Closure Approach ML15308A1072015-11-0505 November 2015 TSTF-505 LAR - NRC Pre-Submittal, November 5, 2015 Meeting Slides ML15279A4992015-10-0808 October 2015 October 8, 2015, Public Meeting Regarding the NFPA-805 License Amendment Application ML15282A0832015-10-0808 October 2015 October 8, 2015, Public Meeting Regarding the NFPA-805 License Amendment Application - Final ML15222A5472015-08-31031 August 2015 GSI 191 Program Chemical Effects Testing Update Option 2b Closure Approach ML15152A0822015-06-0404 June 2015 Presentation for the June 4, 2015 Public Meeting Regarding the National Fire Protection Association Standard 805 License Amendment Request ML14230A9132014-08-18018 August 2014 Enclosure - Fuel Performance and Cask Internals - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L ML14230A9112014-08-18018 August 2014 Enclosure - Example AMP - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 ML14230A9102014-08-18018 August 2014 Enclosure - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 ML14230A9092014-08-18018 August 2014 Enclosure - Generic Concrete AMP CC ISFSI - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 ML14230A9082014-08-18018 August 2014 Enclosure - Elements of an AMP CC ISFSI - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 2024-01-30
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Text
LICENSEE:
Calvert Cliffs Nuclear Power Plant, LLC FACILITY:
Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2
SUBJECT:
SUMMARY OF AUGUST 28,2013, MEETING WITH CONSTELLATION ENERGY GROUP, INC., TO CONTINUE DISCUSSIONS ON THE PROPOSED RISK-INFORMED APPROACH TO THE RESOLUTION OF GENERIC LETIER 2004-02, "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED-WATER REACTORS" WITH A FOCUS ON CHEMICAL EFFECTS TESTING AND SUMP STRAINER BYPASS (TAC NO. MC4672 AND MC4673) On August 28, 2013, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Constellation Energy Group, Inc., the licensee at NRC Headquarters, Three White Flint North, 11601 Landsdown Street, Rockville, Maryland.
The purpose of the meeting was to discuss the licensee's proposed risk-informed approach to the resolution of Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors (PWRs)" with a focus on chemical effects testing and sump strainer bypass for Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 (Calvert Cliffs).
The meeting notice and agenda, dated August 14, 2013, is available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML 13226A090.
A list of attendees is provided as Enclosure 1, but may not be all inclusive.
The licensee discussed (1) the coating bench top autoclave experiment test plan; (2) chemical effects phenomena identification and ranking table (PIRT) items; (3) the debris bypass/penetration Test Plan; and (4) future periodic meetings.
(See Enclosure 2). Discussion of Coating Bench Top Autoclave Experiment Test Plan 1. The NRC staff asked the licensee to confirm that any conclusions about plant-specific coatings drawn from tests performed for other licensees are applicable to the coatings in service at Calvert Cliffs. 2. The coatings document stated that aluminum may have been added in flat or "leaf' form to some epoxy coatings used in reactor containment buildings.
The NRC staff expressed concern that this could result in a significant source term of aluminum not identified by a licensee.
The licensee's contractor stated that the nuclear industry considered these types of coatings early on in the process of reviewing containment materials.
The NRC staff's expectation is that licensees would review their plant specific coating systems and account for any aluminum that may be exposed to the environment following an accident. 3. The licensee's representatives stated that the coatings autoclave tests of unqualified coatings will include plant-specific coatings to ensure they are representative.
- 4. The NRC staff and the licensee discussed whether the types and quantities of species that may leach from a new coating in an autoclave test would be representative of a coating in service for many years at the plant. The licensee thinks the newly applied coating would leach a conservative amount of organic material relative to a coating that has been in service for many years. The NRC staff agreed that freshly applied coatings would likely result in a more conservative test. The licensee stated that they would consider thermal aging of the coatings to reduce the conservatism, but would ensure that any such aging would not result in a non-conservative test. 5. In addition to characterizing materials that may leach from the coatings during autoclave
- testing, the NRC staff stated that it would be appropriate to evaluate whether unqualified coatings could break down during testing and affect head loss in a similar manner to a precipitate.
The NRC staff concern was not that the coatings would be particulate debris, since that is already accounted for, rather that the coatings could become softened or gelatinous in nature. Therefore, the NRC staff and the licensee discussed whether it would be appropriate at some point (e.g., at the test conclusion) to filter a sample of autoclave fluid. The licensee agreed some type of filtering may be appropriate for the test protocol.
- 6. The licensee stated that they were re-evaluating the use of stainless steel coupons as a substrate for coatings.
While this material was originally selected due to excellent corrosion resistance, questions about coating bonding may result in another material being used in the tests. Discussion of PIRT Considerations
- 7. Prior to discussing the open items from the chemical effects PIRT, the NRC staff provided some overall context to the NRC staff's March 2011 PIRT disposition document (ADAMS Accession No. ML 1 02280594).
The goal of this document was to determine whether the NRC should sponsor additional research for any of the remaining chemical effects expert panel PIRT open items. At that time, all plants were assessing chemical effects in a deterministic manner. For some items, the NRC staff used the conservatism built into existing chemical effects evaluations to balance remaining uncertainties and conclude that no additional research was needed. Uncertainties related to chemical effects evaluations become more significant as conservatisms are removed.
- 8. NRC Staff clarified that agreement between the NRC staff and a licensee that a PIRT item is being addressed does not mean that the NRC staff will not have additional questions related to that item during the evaluation of a test method or a test facility.
For example, the NRC staff and industry agree that pH variability, or a range of plausible coolant accident (LOCA) pool pH values, needs to be considered.
In this example, the NRC staff will be looking for Calvert Cliffs to explain the basis for any test pH values and demonstrate how the entire range of plausible post-LOCA pH values is being evaluated. 9. From the NRC staff's perspective, PIRT questions related to radiological effects can be grouped into two categories:
- Effects of radiation on the post-LOCA cooling water (examples
-lowering of pH by radiolysis, increased oxidizing agents such as hydrogen peroxide).
- Effects of radiation on physical and chemical properties (examples could include radiation affecting the structure or properties of formed precipitates or potentially causing embrittlement of fibers affecting debris bed properties).
- 10. The NRC staff stated that the treatment of radiation related PIRT items may depend on the Calvert Cliffs chemical effects evaluation approach.
For example, for a deterministic evaluation the NRC staff precedent has been to balance this uncertainty with known conservatisms in the chemical effects evaluation.
Therefore, NRC staff will need to clearly understand where conservatism has been built into the plant-specific deterministic evaluation.
For a risk-informed chemical effects evaluation, effects of radiation are an additional uncertainty that will need to be considered in the risk informed evaluation.
It is not clear to the NRC staff at this point how this will be factored into the staff's review. The NRC staff has recently started a review on a risk informed pilot plant and we expect that the pilot will establish a precedent for risk informed evaluations.
- 11. With respect to the PIRT Item related to coatings dissolution, the NRC staff stated that the Calvert Cliffs autoclave tests of unqualified coatings are expected to address this open item. 12. Based on the planned plant-specific chemical effects testing supporting the Calvert Cliffs evaluation, the NRC staff has no more questions related to PIRT items on Inorganic Agglomeration or Organic Agglomeration.
Discussion of Debris Bypass/Penetration Test Plan 13. The NRC staff stated that the test plan considers aspects of testing considered important by the NRC. 14. The NRC staff stated that it has not been adequately shown that water chemistry does not affect bypass measurements.
Given a lack of mechanistic understanding concerning how water chemistry affected head loss, the single sensitivity study by South Texas Project does not provide adequate evidence for universal acceptance of non-sensitivity of debris bypass to water quality.
- 15. The NRC staff stated that the test plan discussion of debris type ignores some properties that may affect bypass. Length, flexibility, and potentially other properties may have a significant effect on fiber bypass. The NRC staff noted that mineral wool has been noted to bypass at higher percentages than Nukon. The NRC staff does not understand why Nukon is conservative compared to Thermal Wrap based on fiber diameter.
Nukon has a larger diameter than thermal-wrap, and therefore, may be less likely to bypass if diameter is the controlling characteristic.
The NRC staff requested that the licensee provide additional justification as to why Nukon is an acceptable surrogate for all fiber types. The basis for excluding Temp-Mat and mineral wool should be expanded. 16. The NRC staff stated that they had observed fine fiber prepared using the Nuclear Energy Institute (NEI) methodology that appeared to be excessively agglomerated or inadequately fragmented during preparation.
The NRC staff stated that to ensure consistency with assumptions in the NEI 04-07 guidance, fine fiber preparation should generate a majority of class 2 fibers. 17. The NRC staff stated that the debris filtering relationship is only valid if the debris is mixed homogeneously in the water at the start time, remains homogeneously mixed, and does not settle. The relationship does not evaluate shedding which may or may not be important depending on how the relationship is applied.
Shedding may vary with debris amount on the strainer.
Based on the response to the item below, the NRC staff concluded that there would be adequate time between filter changes and fiber additions to ensure accurate test results.
- 18. The NRC staff questioned when filter changes would be made with respect to the batch introductions.
The licensee stated that there are 15 turnovers and three filter changes, after each of the first 3 batches, and prior to the next batch being introduced.
Based on that schedule, the NRC staff concluded that there would be adequate time to capture all but insignificant amounts of debris, if settling does not occur during the test. If settling occurs more time may be required to remove most of the debris. 19. The NRC staff stated that the assumptions that two 1/8 inch batches will cover the strainer completely should either be verified during testing or by previous
- testing, if it is important to the methodology.
- 20. The NRC staff stated that after initial preparation, the debris should be treated (e.g. stirred adequately) to ensure lack of agglomeration when added to the test. 21. The NRC staff noted that some of the acceptance criteria for parameters controlled or measured during the test may be difficult to attain. 22. The CENG representatives noted that some of the issues discussed during the meeting may be resolved by the industry testing that was performed to evaluate the characteristics of debris that bypasses a strainer. Members of the public were not in attendance.
Public Meeting Feedback forms were not received.
Please direct any inquiries to me at 301-415-1016, adiyah.Morgan@nrc.gov.
Docket Nos. 50-317 and 50-318
Enclosures:
- 1. List of Attendees
- 2. Licensee Handout cc w/encls:
Distribution via Listserv Nadiyah S. Morgan, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation LIST OF ATTENDEES AUGUST 28. 2013. MEETING WITH CONSTELLATION ENERGY GROUP, INC. CHEMICAL EFFECTS IN RISK-INFORME GL 2004-02 RESOLUTION CALVERT CLIFFS NUCLAR POWER PLANT, UNIT NOS. 1 AND 2 , NAME : Nadiyah Morgan I Paul Klein 1 Stephen Smith John Burke 'Ken Greene
- Josh Wargo I Tom Konerth ! Anne Lederer ; Gilbert Zigler i Jon Cavallo :Time Sande Enercon Services, Inc. Underwater Engineering
- Services, Inc. i Enercon Services, Inc. Enclosure 1
CENGSM a joint venture of-------
0 Constellation
.,.* .... eoF Energy, "' Calvert Cliffs Chemical Effects in Informed GSI-191 Resolution Fifth Discussion With NRC Staff August 28, 2013 *
Agenda *
- Discussion of Chemical Effects PIRT Items
- Discussion of Alkyds Autoclave Test Plan
- Discussion of Debris Bypass/Penetration Test Plan *
- Schedule for future periodic meetings CENG, .. a 101nt venture of I 0 Constellation
.,_ *-eoF Energy """"
- Tom Konerth-Supervisor Mechanical Design
- Anne Lederer-Mechanical Design Engineer
- Ken Greene-Licensing Engineer
- John Swailes-Project Manager GSI-191
- Craig Sellers-Project Manager Rl GSI-191 *
- Jon Cavallo-Coatings Consultant
- Gil Zigler-Debris Bypass/Penetration Tests CENG., a JOint venture of I 0 eonoteUatlon
.. * ... eoF .. _.,.,.
- Review & Work Towards Agreement on Remaining Chemical Effects PIRT Issues-CCNPP-CHLE-003
- Review & Work Towards Agreement on Alkyd Autoclave Test Plan-CCNPP-CHLE-007
- Review & Work Towards Agreement on Strainer Bypass/ Penetration Test Plan-CCNPP-BPPian-001
- Present Proposed Schedule for Future Meetings
- Capture Staff Issues and Concerns CENG, ..
a JOint venture of I 0 Constellation
.. * ... eoF Energy "'" ..
Remaining Chemical Effects PIRT Issues
- PIRT Item 2.1 Radiolytic Environment
-Plan to add Strong Acids at Predicted Rate of Production
- PIRT Item 2.5 Addit'l Debris Bed Chemical Reactions
-Fiberglass
& Metals Insensitive
-Irradiation is not expected to have a chemical effects impact on coatings
-Zinc and Epoxy Coatings Not Sensitive
-Alkyd Coatings to be addressed in Autoclave Test
a 101nt venture of I 0 eonst..uatlon
... * ... eDF *
- Alkyds Autoclave Test Plan-CCNPP-CHLE-007
- Investigate Dissolution/Leaching from Alkyd Coatings
-Apply Alkyd Coatings to SS Coupons -Submerge in Borated Water -Dissolve Buffer at 195°F -Expose to LOCA Temperature Profile for 48 Hours -Chemical Analysis for Potential Precipitants
- Section-by Section Review CENG_. a 1o1nt venture of------, 0 Constellation
... *:"'eDF "'-llY .. * * {)
Bypass Test Plan-CCNPP-BPPian-001
- Prototypical Strainer Module -Fabricated from Spare Parts
- LDFG (Nukon) Debris -Temp-Mat Quantity<
5% -Mineral Wool< 10%
- NEI Pressure-Wash Debris Preparation
- Section-by Section Review CENG .. a JO<nt venture of I 0
... * .... eoF f:nervy "*' ... * * '
Other Items
- Assumption of 10 11m Sphere Particulate
-Surface Area of 10 lim Particulate Debris Results in Unusually Large Surface Area of These Materials
-Working on Resolution Approach
- Submit for Discussion Soon
- Others? CENG" a 10int vecture ot I 0 c-stellation
.. *-eoF Enlwgy """ * * ,, {'}
Schedule for Future Periodic Meeting ..
- September 2013 -Interim Bench-Top Test Results -Approach to 10 Particulate Debris
- December 2013/January 2014 -Chemical Effects Bench-Top Test Results -Final Chemical Effects Screening Test Proto.col
.. -Strainer Bypass/Penetration Test Results CENG, a 1o,nt venture of I 0 eonsteo.ation
.,. t "'eDF Energy "". ..... ,. (j
- Members of the public were not in attendance.
Public Meeting Feedback forms were not received.
Please direct any inquiries to me at 301-415-1016, or Nadiyah.Morgan@nrc.gov.
Ira/ Nadiyah S. Morgan, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318
Enclosures:
- 1. List of Attendees
- 2. Licensee Handout cc w/encls:
Distribution via Listserv DISTRIBUTION:
PUBLIC LPLI-1 RIF RidsAcrsAcnw_MaiiCTR RidsNrrDorl RidsNrrDoriLpli-1 RidsNrrPMCalvertCiiffs RidsNrrLAKGoldstein RidsRgniMaliCenter JStang, NRR PKiein, NRR MYoder, NRR SSmith, NRR ADAMS Accession No. ML 133108929 OFFICE DORL/LPLI-1/PM DORL/LPLI-1/LA DE/ESGB/BC NAME NMorgan KGoldstein GKulesa DATE 11/13/2013 11/13/2013 11/18/2013 TWertz, NRR DRich, EDO Region I RidsNrrDeEsgb EWong, NRR JBurke, RES RidsNrrDssSsib DSS/SSIB/BC DORLILPLI-1/BC JStang BBeasley 11/25/2013 12/6/2013 OFFICIAL RECORD COPY