|
---|
Category:Slides and Viewgraphs
MONTHYEARML24310A0672024-11-0505 November 2024 Constellation NRC Pre-Submittal Meeting Slides - Proposed Alternative for Reactor Vessel Closure Stud Exam Optimization ML24137A1882024-05-16016 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) ML23262B2602023-09-19019 September 2023 Slides - Constellation - Pre-Application EP 9/25/2023 Meeting Handout 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 ML23103A4072023-04-13013 April 2023 Presentation Slides for Information Call on 4/13/23 N2E Recirc Discharge Nozzle Weld Repair 2nd Request for Alternative ML23080A2972023-03-21021 March 2023 Presentation Slides for Information Call on 3/21/23 N2E Recirc Discharge Nozzle Weld Repair Request for Alternative 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 ML22305A5922022-11-0303 November 2022 Pre-Submittal Meeting Presentation Slides - Risk Informed Completion Time (TSTF-505) and Risk Informed Categorization and Treatmentof SSCs (10 CFR 50.69) Proposed License Amendments-Updated ML22301A0132022-11-0303 November 2022 Pre-Submittal Meeting Presentation Slides - Risk Informed Completion Time (TSTF-505) and Risk Informed Categorization and Treatmentof SSCs (10 CFR 50.69) Proposed License Amendments ML22222A1122022-08-0404 August 2022 NMP1 Torus Corrosion Presentation for August 2022 Final 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 ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML21162A3322021-06-11011 June 2021 BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a 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 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 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) ML20098D5082020-04-0909 April 2020 AST LOCA Approach to Elemental Iodine Removal - NRC Public Meeting on RAI 6 - April 9, 2020 ML20022A0262020-01-22022 January 2020 NEI Presentation Status Update for Ropte Short Term Action Plan: Removed Planned Unavailability for Mitigating Systems Performance Index ML19158A1202019-06-10010 June 2019 Rict & 50.69 LARs NRC Pre-submittal Meeting ML19133A0912019-04-22022 April 2019 Supplement to Containment Oxygen Concentration License Amendment Request 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 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 ML17325A2772017-11-28028 November 2017 November 28, 2017 Pre-Submittal Teleconference Re Planned TSTF-542 LAR Presentation ML17306A0842017-11-0606 November 2017 Meeting Slide for Teleconference with Exelon Generation Company, LLC - Criticality Analysis for NMP1 Boraflex Racks: No Boraflex Credit, 3 Out of 4 Loading, and Cell Blockers ML16153A3442016-06-0101 June 2016 Oswego Chamber of Commerce Assessment Meeting Presentation ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML14084A5342014-03-26026 March 2014 Nrc/Nei Presentation Slides: 13-02 OIP Template Update ML13340A0912013-11-0101 November 2013 Regulatory Conference/Public Meeting - Loss of Shutdown Cooling - Ceng Presentation/Slides ML13059A3742013-03-13013 March 2013 Summary of Category 1 Public Meeting with Nine Mile Point Nuclear Station, Unit 2 Representatives to Discus Planned Amendment Request on Implementation of Mellla+ ML1212100442012-04-0303 April 2012 Meeting Slides - NFPA-805 Pre-Application Meeting with NRC Staff April 3, 2012 ML1113605612011-05-16016 May 2011 NRC Meeting Slides, Nine Mile Point & Fitzpatrick 2011 Annual Assessment Meeting ML0926506592009-09-15015 September 2009 Slides from the Public Meeting with Constellation Energy - Nine Mile Point ISFSI Presentation ML0827705652008-10-27027 October 2008 Extended Power Uprate Pre-Application Meeting Slides ML0827503872008-09-29029 September 2008 Enclosure 2 Meeting Slides ML0811403012008-04-23023 April 2008 NRC Annual Performance Assessment Meeting ML0807901872008-03-18018 March 2008 NRC Annual Performance Assessment Slides, 2007 Reactor Oversight Program ML0712704232007-04-24024 April 2007 Constellation Slides - Nine Mile Point Meeting Annual Assessment Summary 2006-07 ML0710100842007-04-10010 April 2007 Slides for 04/24/2007 Nine Mile Point Annual Assessment Meeting ML0634800282006-12-0404 December 2006 Slides, Nine Mile Point 1 Alternate Source Term, from Nrc/Constellation Energy Meeting 2024-05-16
[Table view] |
Text
NRC Annual Assessment Meeting For Nine Mile Point Nuclear Regulatory Commission - Region I Scriba, New York April 26, 2006 2
Purpose of Todays Meeting
- A public forum for discussion of Constellations performance with respect to the safe operation of the Nine Mile Point plants.
- The NRC will present its assessment of Constellations performance with respect to the safe operation of the Nine Mile Point plants.
- 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
- Constellation 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
- Edward Knutson, Resident Inspector 6
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 Regulatory Licensee Degraded Response Response CornerstoneMultiple/Rep.
Degraded Performance CornerstoneUnacceptable
- Increasing Safety Significance
- Increasing NRC Inspection Efforts
- Increasing NRC/Licensee Management Involvement
- Increasing Regulatory Actions
9 1
Examples of Baseline Inspections
- 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 Assessment Results January 1, 2005 - December 31, 2005
- Operated safely throughout the Assessment Period
- Licensee Response column of the Action Matrix for all of 2005
- NRC will conduct baseline inspections during the remainder of the cycle 14 Assessment Bases January 1, 2005 - December 31, 2005
- All Site Performance Indicators Green
- All Inspection Findings Green
- 8 findings of very low safety significance (Green)
- 1 of the 9 findings was common to both units
15 Nine Mile Unit 1 Indicators Available On The Web At: http://www.nrc.gov/reactors/operating/oversight.html 16 Nine Mile Unit 2 Indicators Available On The Web At: http://www.nrc.gov/reactors/operating/oversight.html
17 Performance Indicator Example Available On The Web At: http://www.nrc.gov/reactors/operating/oversight.html 18 NRC Inspection Activities January 1, 2005 - December 31, 2005
- 5549 hours0.0642 days <br />1.541 hours <br />0.00917 weeks <br />0.00211 months <br /> of inspection related activities
- 3 resident inspectors assigned to the site
- 10 regional specialist inspector visits
- emergency preparedness exercise evaluation
- license renewal aging management
- problem identification and resolution
19 Nine Mile Unit 1 Findings Available On The Web At: http://www.nrc.gov/reactors/operating/oversight.html 20 Nine Mile Unit 2 Findings Available On The Web At: http://www.nrc.gov/reactors/operating/oversight.html
21 Licensee Response and Remarks Nine Mile Point Nuclear Station Constellation Generation Group 22 Summary Of NRC Assessment
- Constellation Operated the Nine Mile Point Plants In A Manner That Preserved Public Health and Safety During 2005
- NRC Will Conduct Baseline Inspections At Both Nine Mile Point Plants During 2006
23 Contacting the NRC
- To report an emergency (301) 816-5100 (call collect)
- To report a safety concern (800) 695-7403 or Allegation@nrc.gov