|
---|
Category:Slides and Viewgraphs
MONTHYEARML24137A1882024-05-16016 May 2024 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML24100A7672024-04-11011 April 2024 Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2 ML24089A2612024-04-0909 April 2024 Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041) ML24029A1742024-01-30030 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 2024-05-16
[Table view] |
Text
NRC Annual Assessment Meeting For Calvert Cliffs Nuclear Regulatory Commission - Region I Prince Frederick, Maryland April 20, 2006 2
Purpose of Todays Meeting
- A public forum for discussion of the licensees performance
- The NRC will present its assessment of safety performance at Calvert Cliffs during 2005
- Constellation will be given the opportunity to respond and describe new or existing programs to maintain or improve its performance
3 Agenda
- Review of Reactor Oversight Process
- National Summary of Plant Performance
- Discussion of Plant Performance Results
- Licensee Response and Remarks
- NRC available to address public questions 4
Region I Organization NRC Region I Samuel J. Collins, Regional Administrator Marc L. Dapas, Deputy Regional Administrator Director Division of Reactor Projects Director Division of Reactor Safety Brian E. Holian, Director A. Randolph Blough, Director David C. Lew, Deputy Director Marsha K. Gamberoni, Deputy Director Projects Branch 1 Regional Specialist Branches Brian J. McDermott, Chief Calvert Cliffs Nine Mile Point Ginna Project Engineers Resident Inspectors Resident Inspectors Resident Inspectors Arthur Burritt Mark Giles Leonard Cline Kenneth Kolaczyk Heather Jones Marlone Davis Brian Fuller Mark Marshfield Edward Knutson
5 NRC Representatives
- Brian J. McDermott, Chief, Projects Branch 1, Region I
- Mark A. Giles, Senior Resident Inspector
NRC Performance Goals
- Safety: Ensure protection of the public health and safety and the environment
- Security: Ensure the secure use and management of radioactive materials
- Openness: Ensure openness in our regulatory process
- Effectiveness: Ensure that NRC actions are effective, efficient, realistic, and timely
- Management: Ensure excellence in agency management to carry out the NRCs strategic objectives
7 Reactor Oversight Process Strategic Strategic PerformanceAreas Performance Areas Safety Safety Cornerstones Cornerstones Baseline Inspection Performance Indicator Results Results Significance Significance Threshold Threshold ActionMatrix Action Matrix Regulatory Response 8
Action Matrix Concept Licensee Regulatory Degraded Multiple/Rep. Unacceptable Response Response Cornerstone Degraded Performance Cornerstone L icen s R egulato ry eD ed grad lti p M u le/R .U ac ep n tab lc R esp on eR esp on e e ton orn C es ga ston eD orn C ed r rfoeP c an rm
- Increasing Safety Significance
- Increasing NRC Inspection Efforts
- Increasing NRC/Licensee Management Involvement
- Increasing Regulatory Actions
9 Examples of Baseline Inspections 1
- Equipment Alignment ~80 hrs/yr
- Triennial Fire Protection ~200 hrs/3 yrs
- Operator Response ~125 hrs/yr
- Rad Release Controls ~110 hrs/2 yrs
- Engineering Design ~680 hrs/2 yrs
- Corrective Action Program ~250 hrs/2 yrs
- Corrective Action Case Reviews ~60 hrs/yr 1Baseline Inspections For A Single Unit Require Approximately ~5000 Hours Per Year 10 Significance Threshold Inspection Findings Green: Very low safety significance White: Low to moderate safety significance Yellow: Substantial safety significance Red: High safety significance Performance Indicators Green: Baseline Inspection White: Increased NRC oversight Yellow: Requires more NRC oversight Red: Requires more NRC oversight
11 National Summary Status At End Of 2005 2004 Licensee Response 84 78 Regulatory Response 12 21 Degraded Cornerstone 4 0 Multiple/Repetitive Degraded Cornerstone 3 3 Unacceptable 0 0 Total 103 102*
- Davis-Besse was in Shutdown with Enhanced Oversight in 2004 12 National Summary Total Inspection Findings Total For Calendar Year 2005 2004 Green 849 778 White 10 11 Yellow 1 0 Red 0 0 Performance Indicator Results Status At End Of 2005 2004 Green 1850 1834 White 4 6 Yellow 0 0 Red 0 0
13 NRC Inspection Activities January 1, 2005 - December 31, 2005
- 5378 hours0.0622 days <br />1.494 hours <br />0.00889 weeks <br />0.00205 months <br /> of inspection related activities
- 2 resident inspectors assigned to the site
- 9 regional specialist inspector visits
15 Calvert Cliffs 2 Indicators Available On The Web At: http://www.nrc.gov/reactors/operating/oversight.html 16 Performance Indicator Example Available On The Web At: http://www.nrc.gov/reactors/operating/oversight.html
17 Unit 1 Assessment Results January 1, 2005 - December 31, 2005
- Operated safely throughout the Assessment Period
- Licensee Response column of the Action Matrix for the last three quarters of 2005
- Inspection Findings 4 findings of very low safety significance (Green) 2 of the 4 findings were common to both units
- NRC will conduct baseline inspections during the remainder of the cycle 18 Unit 2 Assessment Results January 1, 2005 - December 31, 2005
- Operated safely throughout the Assessment Period
- Licensee Response column of the Action Matrix last three quarters of 2005, Regulatory Response column in the 1st Quarter of 2005
- Inspection Findings 4 findings of very low safety significance (Green) 2 of the 4 findings were common to both units
- NRC will conduct baseline inspections during the remainder of the cycle
19 Unit 2 Assessment Results
- 1 finding of low to moderate safety significance (White - Issued 2nd Quarter 2004)
Relay failure causing steam dump valves to fail open following reactor trip
- Supplemental inspection in January 2005 determined Constellations root cause analysis was complete and corrective actions were appropriately identified
21 Calvert Cliffs 2 Findings Available On The Web At: http://www.nrc.gov/reactors/operating/oversight.html 22 Licensee Response and Remarks Calvert Cliffs Nuclear Power Plant Constellation Generation Group
23 Summary Of NRC Assessment
- Constellation Operated Calvert Cliffs In A Manner That Preserved Public Health and Safety During 2005
- NRC Will Conduct Baseline Inspections At Calvert Cliffs During 2006 24 Contacting the NRC
- To report an emergency (301) 816-5100 (call collect)
- To report a safety concern (800) 695-7403 or Allegation@nrc.gov
- General information or questions www.nrc.gov Select What We Do for Public Affairs
25 Reference Sources Reactor Oversight Process http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html Public Electronic Reading Room http://www.nrc.gov/reading-rm.html Public Document Room 1-800-397-4209 (Toll Free)