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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
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NRC Annual Performance Assessment of Nine Mile Point 2006 Reactor Oversight Program
Purpose of Todays Meeting z NRC will address Constellations performance as described in the annual assessment letter z Constellation will be given the opportunity to respond to the information in the letter and inform the NRC of new or existing programs to maintain or improve their performance z NRC will be available to engage interested stakeholders on performance of the plant and our role in ensuring safe plant operations 2
Agenda z Introduction and NRC Organization z Review of NRC Reactor Oversight Process z Regulatory Summary of National Plant Performance z NRC Assessment of Plant Performance Results z Constellation Response and Remarks z NRC Closing Remarks z Break z NRC available to address public questions 3
Region I Organization Samuel J. Collins Regional Administrator Marc L. Dapas Deputy Regional Administrator David C. Lew Marsha K. Gamberoni Director Division of Reactor Projects Director Division of Reactor Safety James W. Clifford Darrell J. Roberts Deputy Director Deputy Director Glenn Dentel Branch Chief Regional Specialists Project Engineers Resident Inspectors Brice Bickett Leonard Cline Heather Jones Ed Knutson 4
NRC Representatives z Glenn Dentel, Branch Chief
- (603) 474-3580 z Leonard Cline, Senior Resident Inspector Ed Knutson, Resident Inspector
- (315) 342-4041 z Brice Bickett, Senior Project Engineer
- (610) 337-6959 z Douglas Pickett, Project Manager, NRR
- (301) 415-1364 5
NRC Performance Goals z Safety: Ensure protection of the public health and safety and the environment z Security: Ensure the secure use and management of radioactive materials z Openness: Ensure openness in our regulatory process z Effectiveness: Ensure that NRC actions are effective, efficient, realistic, and timely z Management: Ensure excellence in agency management to carry out the NRCs strategic objective 6
Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Baseline Inspection Performance Indicator Results Results Significance Significance Threshold Threshold Action Matrix Regulatory Response 7
Examples of Baseline Inspection Areas z Equipment Alignment z Maintenance z Fire Protection z Operator Response z Emergency Preparedness z Radiation Release Controls z Worker Radiation Protection z Corrective Action Program z Corrective Action Case Reviews 8
Significance Threshold Performance Indicators Green: Baseline Inspection White: May increase NRC oversight Yellow: Requires more NRC oversight Red: Requires more NRC oversight Inspection Findings Green: Very low safety issue White: Low to moderate safety issue Yellow: Substantial safety issue Red: High safety issue 9
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 10
Regulatory Summary of National Plant Performance Status at End of 2006 Licensee Response 70 Regulatory Response 24 Degraded Cornerstone 6 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total 103 11
National Summary z Performance Indicator Results (at end of 2006)
Green 1843 White 11 Yellow 0 Red 0 z Total Inspection Findings (2006)
Green 676 White 13 Yellow 0 Red 0 12
NRC Inspection Activities at Nine Mile Point in 2006 8021 Hours of inspection and assessment related activities z Two resident inspectors assigned to the site Specialist Inspections
- 8 regional inspections
- 2 team inspections 13
NRC Inspection Activities at Nine Mile Point in 2006 Daily Resident Inspections Refueling outage (March 20 - April 13) z Component Design Bases Inspection z Triennial Fire Protection Inspection 14
2006 NRC Assessment of Nine Mile Point z Unit 1 - Licensee Response Column z Unit 2 - Licensee Response Column z Inspection Findings
-Four Findings of very low safety significance (Green) z All performance indicators were green (very low safety significance) in 2006 15
NRC 1st Quarter 2007 Assessment Follow-up z 2006 Annual Assessment Letter (March 2007)
- Preliminary White Finding - Unit 1 Licensed Operator Requalification Training z 1st Quarter 2007 Assessment Follow-up Letter (April 2007)
- Final White Finding - Unit 1 Licensed Operator Requalification Training
- Unit 1 - Regulatory Response Column of Action Matrix
- November 2007 - Supplemental Inspection 95001 16
NRC Annual Assessment Summary at Nine Mile Point z Constellation operated Nine Mile Point in a manner that preserved public health and safety.
z All cornerstone objectives were met.
z NRC plans baseline inspections for the 2007 assessment period and one supplemental inspection to review Constellations response to the Unit 1 Licensed Operator Requalification Training White finding.
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Nine Mile Point Response and Remarks Kevin Nietmann Site Vice President - Nine Mile Point Constellation Energy LLC 18
Contacting the NRC z Report an emergency (301) 816-5100 (call collect) z Report a safety concern:
(800) 695-7403 Allegation@nrc.gov z General information or questions www.nrc.gov 19
Reference Sources z Reactor Oversight Process http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html z Public Electronic Reading Room http://www.nrc.gov/reading-rm.html z Public Document Room 1-800-397-4209 (Toll Free) 20
END OF THE PRESENTATION Nuclear Regulatory Commission - Region I King of Prussia, Pennsylvania April 24, 2007 21