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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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Annual Assessment Meeting Calvert Cliffs Reactor Oversight Program - Cycle 3 Nuclear Regulatory Commission - Region I King of Prussia, PA
Agenda
! Introduction
! Review of Reactor Oversight Process
! National Summary of Plant Performance
! Discussion of Plant Performance Results
! General Topic: Security Update
! Licensee Response and Remarks
! NRC Closing Remarks
! Meeting with the Licensee adjourned
! NRC available to address questions from the public
Region I Organization Hubert Miller Regional Administrator James Wiggins Deputy Regional Administrator A. Randolph Blough Wayne Lanning Director Division of Reactor Projects Director Division of Reactor Safety John Rogge Richard Crlenjak Acting Deputy Director Deputy Director Jim Trapp Regional Specialists Branch Chief Calvert Cliffs Nine Mile Point Ginna Resident Inspectors Resident Inspectors Resident Inspectors Fred Bower Gordon Hunegs Ken Kolaczyk Joe OHara Brian Fuller Mark Marshfield Ed Knutson
NRC Representatives
! Jim Wiggins, Deputy Region Administrator, Region I
< (610) 337-5340
! Jim Trapp, Branch Chief
< (610) 337-5186
! Fred Bower, Acting Senior Resident Inspector
< (410) 586-2626
! Joe OHara, Resident Inspector
< (410) 586-2626
Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Performance Indicator Baseline Inspection Results Results Significance Significance Threshold Threshold Action Matrix Regulatory Response
Action Matrix Concept Licensee Regulatory Degraded Multiple/Rep. Unacceptable Response Response Cornerstone Degraded Performance Cornerstone Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions
Significance Threshold Inspection Findings/Perf. Indicator Green: Very Low safety issue Baseline Inspection White: Low to moderate safety issue Supplemental Inspection (95001)
Yellow: Substantial safety issue Supplemental Inspection (95002)
Red: High safety issue Supplemental Inspection (95003)
Examples of Baseline Inspections
! Performance Indicator Verification
! Resident Baseline Inspections
< Fire Protection
< Maintenance and Surveillance
< Operability Evaluation
! Region Led Baseline Inspections
< Team Inspections
- Safety System Design Inspection (SSDI)
- Problem Identification and Resolution (PI&R)
- Emergency Planning
< Operator Training
< Security
< Radiological Controls
National Summary of Plant Performance Licensee Response 56 Regulatory Response 37 Degraded Cornerstone 6 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total Plants 102
National Summary
! Performance Indicator Results (at end of ROP Cycle 3)
< Green 1835
< White 5
< Yellow 0
< Red 0
! Total Inspection Findings (ROP Cycle 3)
< Green 783
< White 30
< Yellow 1
< Red 2
Calvert Cliffs Unit 1 Assessment Results (Jan 1 - Dec 31, 2002)
! Operated safely throughout the Assessment Period
! Regulatory Response column of the Action Matrix for the last two quarters of 2002 (cornerstone objectives met with minimal reduction in safety margin)
! Degraded Cornerstone column of the Action Matrix for first two quarters of 2002 (cornerstone objectives met with moderate degradation in safety performance)
! Problem Identification and Resolution Substantive Crosscutting Issue Closed
! NRC will conduct baseline inspections during the next cycle
Calvert Cliffs Unit 2 Assessment Results (Jan 1 - Dec 31, 2002)
! Operated safely throughout the Assessment Period
! Regulatory Response column of the Action Matrix for the last three quarters of 2002 (cornerstone objectives met with minimal reduction in safety margin)
! Licensee Response column of the Action Matrix for first quarter of 2002 (cornerstone objectives fully met)
! NRC will conduct baseline inspections during the next cycle
Unit 1 - 4Q Performance Indicators WWW.NRC.GOV then click Reactor Oversight Process
Unit 2 - 4Q Performance Indicators WWW.NRC.GOV then click Reactor Oversite Process
Typical Performance Indicator WWW.NRC.GOV then click Reactor Oversight Process
Calvert Cliffs Inspection Activities (Jan 1 - Dec 31, 2002)
! 5427 hours0.0628 days <br />1.508 hours <br />0.00897 weeks <br />0.00206 months <br /> of inspection related activities
! 2 resident inspectors assigned to the site
! 22 regional inspector visits
< Included 3 team inspections (SSDI, PI&R, EP)
! Inspection Findings (common for both Units)
< 4 findings of very low safety significance (Green)
< 2 findings of low to moderate safety significance (White)
Unit 1 - Inspection Results WWW.NRC.GOV then click Reactor Oversight Process
Unit 2 - Inspection Results WWW.NRC.GOV then click Reactor Oversight Process
Unit 1 - Action Matrix Unit 2 - Action Matrix NRC Self-Improvement Efforts
! Security Enhancements
! Significance Determination Process Task Group
! Performance Indicator Program
! Davis-Besse Lessons Learned Task Force
NRC Security Program Update
! NRC has issued Interim Compensatory Measures and NRC Orders
! Office of Nuclear Security and Incident Response Formed (NSIR - April 2002)
! Threat Advisory and Protective Measure System
! Access Authorization Order (January 7, 2003)
! Force-on-Force Exercises (February 2003)
! Training Order (TBD)
! Fatigue Order (TBD)
! Design Basis Threat (TBD)
Reference Sources
! Reactor Oversight Process
< http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html
! Public Electronic Reading Room
< http://www.nrc.gov/reading-rm/adams.html
! Public Document Room
< 1-800-397-4209 (Toll Free)