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| | number = ML072050220 | | | number = ML072050220 |
| | issue date = 05/03/2007 | | | issue date = 05/03/2007 |
| | title = 05/03/2007 Public Meeting Slides for Catawba | | | title = Public Meeting Slides for Catawba |
| | author name = | | | author name = |
| | author affiliation = NRC/RGN-II/DRP | | | author affiliation = NRC/RGN-II/DRP |
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| =Text= | | =Text= |
| {{#Wiki_filter:NRC CY2006 Annual Assessment Meeting Catawba Nuclear Station Rock Hill, SC Rock Hill, SC May 3, 2007 May 3, 2007 Purpose of Today's Meeting | | {{#Wiki_filter:NRC CY2006 Annual Assessment Meeting Catawba Nuclear Station Rock Hill, SC May 3, 2007 |
| **Provide a public forum for discussion of Provide a public forum for discussion of Catawba performanceCatawba performance | | |
| **NRC will address Catawba performance NRC will address Catawba performance issues identified in the annual assessment issues identified in the annual assessment letter letter**Catawba management will be given the Catawba management will be given the opportunity to respond to the information in opportunity to respond to the information in the letter and inform the NRC of new or the letter and inform the NRC of new or existing programs to maintain or improve existing programs to maintain or improve their performance their performance Agenda*Introduction | | Purpose of Todays Meeting |
| *Review of Reactor Oversight Process | | * Provide a public forum for discussion of Catawba performance |
| *National Summary of Plant Performance | | * NRC will address Catawba performance issues identified in the annual assessment letter |
| *Discussion of Catawba Plant Performance Results*Catawba Management Response and Remarks | | * Catawba management 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 |
| *NRC Closing Remarks | | |
| *Break*NRC Available to Addr ess Public Questions Region II OrganizationWilliam TraversRegional Administrator Victor McCreeDeputy Regional AdministratorCharles CastoDirector Division of Reactor ProjectsHarold ChristensenDeputy DirectorJoseph SheaDirector Division of Reactor SafetyKrissKennedyDeputy DirectorJim MoormanBranch ChiefRegional SpecialistsCatawba Nuclear StationAndrew Sabisch; SRIGordon Williams, RILee Harmon, OAProject EngineerCurt Rapp, SPE NRC Performance GoalsEnsure protection of the public health and safety and the environmentEnsure the secure use and management of radioactive materials PRIMARY GOALS OTHER GOALS | | Agenda |
| *Ensure openness in NRC regulatory process | | * Introduction |
| *Ensure that NRC actions are effective, efficient, realistic, and timely | | * Review of Reactor Oversight Process |
| *Ensure excellence in NR C management to carry out the NRC's strategic objective Reactor Oversight ProcessThe NRC monitors plant performance The NRC monitors plant performance in three major areas: | | * National Summary of Plant Performance |
| in three major areas:Reactor Safety Reactor Safety(avoiding accidents or (avoiding accidents or transient & reducing their consequences if transient & reducing their consequences if they occur)they occur)Radiation Safety Radiation Safety(both plant workers & the (both plant workers & the public during routine operations)public during routine operations)Security Security(protection of the plant against (protection of the plant against sabotage or other security threats) . . . . .
| | * Discussion of Catawba Plant Performance Results |
| sabotage or other security threats) . . . . . Major changes in the postMajor changes in the post
| | * Catawba Management Response and Remarks |
| --9/11 environment9/11 environment Reactor Oversight Process Reactor Oversight ProcessThe ROP includes two separate sources of The ROP includes two separate sources of information:information:
| | * NRC Closing Remarks |
| **Inspections conducted by NRC personnel Inspections conducted by NRC personnel | | * Break |
| **Performance Indicators developed from data Performance Indicators developed from data provided by licenseesprovided by licenseesInspectors can be Site Inspectors can be Site | | * NRC Available to Address Public Questions |
| --based or Regionbased or Region
| | |
| --basedbasedTogether they provid e a composite picture Together they provid e a composite picture of how the plant is being operated of how the plant is being operated Examples of Baseline InspectionsEquipment Alignment ~80 hrs/yr Triennial Fire Protection ~200 hrs every 3 yrsOperator Response ~125 hrs/yrEmergency Preparedness ~80 hrs/yrRad Release Controls ~110 hrs every 2 yrsWorker Radiation Protection ~90 hrs/yrCorrective Action Program ~250 hrs every 2 yrsCorrective Action Case Reviews ~60 hrs/yr | | Region II Organization William Travers Regional Administrator Victor McCree Deputy Regional Administrator Charles Casto Joseph Shea Director Division of Reactor Projects Director Division of Reactor Safety Harold Christensen Kriss Kennedy Deputy Director Deputy Director Jim Moorman Regional Specialists Branch Chief Catawba Nuclear Station Project Engineer Andrew Sabisch; SRI Curt Rapp, SPE Gordon Williams, RI Lee Harmon, OA |
| --RETS/ODCM Radiological EffluentRETS/ODCM Radiological EffluentPublic Radiation SafetyPublic Radiation SafetyPERFORMANCE INDICATORSPERFORMANCE INDICATORSCORNERSTONECORNERSTONE
| | |
| --Physical Protection (not publicly available)Physical Protection (not publicly available)SafeguardsSafeguards
| | NRC Performance Goals PRIMARY GOALS Ensure protection of the public health and safety and the environment Ensure the secure use and management of radioactive materials OTHER GOALS |
| --Occupational Exposure ControlOccupational Exposure ControlOccupational Radiation Occupational Radiation SafetySafety--Drill/Exercise PerformanceDrill/Exercise Performance | | *Ensure openness in NRC regulatory process |
| --ERO Drill ParticipationERO Drill Participation | | *Ensure that NRC actions are effective, efficient, realistic, and timely |
| --Alert and Notification SystemAlert and Notification SystemEmergency PreparednessEmergency Preparedness
| | *Ensure excellence in NRC management to carry out the NRCs strategic objective |
| --Reactor Coolant ActivityReactor Coolant Activity
| | |
| --Reactor Coolant System LeakageReactor Coolant System LeakageBarrier IntegrityBarrier Integrity
| | Reactor Oversight Process The NRC monitors plant performance in three major areas: |
| --Safety System Functional FailureSafety System Functional Failure | | Reactor Safety (avoiding accidents or transient & reducing their consequences if they occur) |
| --Emergency AC Power SystemEmergency AC Power System
| | Radiation Safety (both plant workers & the public during routine operations) |
| --High Pressure Injection SystemHigh Pressure Injection System
| | Security (protection of the plant against sabotage or other security threats) . . . . . |
| --Heat Removal SystemHeat Removal System
| | Major changes in the post-9/11 environment |
| --Residual Heat Removal SystemResidual Heat Removal System
| | |
| --Cooling Water SystemsCooling Water SystemsMitigating SystemsMitigating Systems
| | Reactor Oversight Process Reactor Oversight Process The ROP includes two separate sources of information: |
| --Unplanned ScramsUnplanned Scrams | | * Inspections conducted by NRC personnel |
| --Scrams with Loss of Normal Heat SinkScrams with Loss of Normal Heat Sink | | * Performance Indicators developed from data provided by licensees Inspectors can be Site-based or Region-based Together they provide a composite picture of how the plant is being operated |
| --Unplanned Power ChangesUnplanned Power ChangesInitiating EventsInitiating Events Reactor Oversight ProcessSafetyCornerstonesBaseline Inspection ResultsSignificance ThresholdAction MatrixSignificance ThresholdPerformance IndicatorResultsStrategicPerformance AreasSafetyCornerstonesBaseline Inspection ResultsSignificance ThresholdAction MatrixSignificance ThresholdPerformance IndicatorResultsNRC ResponseStrategicPerformance Areas Thresholds Safety Significance Green:Very low safety issueWhite:Low-to-moderate safety issue Yellow:Substantial safety issue Red:High safety issue NRC Inspection Efforts Green:Only Baseline InspectionsWhite:May increase NRC oversight Yellow:Increased NRC oversight Red:Increased NRC oversight and other NRC actions Action Matrix ConceptLicenseeResponseRegulatoryResponseDegradedCornerstoneMultiple/Rep.DegradedCornerstoneUnacceptablePerformance Increasing Safety SignificanceIncreasing NRC Inspection Efforts Increasing NRC/Licensee Management Interaction and InvolvementIncreasing Regulatory Actions National Summary of Nuclear Plant PerformanceStatus at End of CY 2006Licensee Response 70Regulatory Response 24 Degraded Cornerstone 6 Multiple/Repetitive Degraded Cornerstone3 Unacceptable 0Total . . . . . . . . . . . . . . . . . .103 Catawba CY2006 NRC Inspection Activities | | |
| | Examples of Baseline Inspections z Equipment Alignment ~80 hrs/yr z Triennial Fire Protection ~200 hrs every 3 yrs z Operator Response ~125 hrs/yr z Emergency Preparedness ~80 hrs/yr z Rad Release Controls ~110 hrs every 2 yrs z Worker Radiation Protection ~90 hrs/yr z Corrective Action Program ~250 hrs every 2 yrs z Corrective Action Case Reviews ~60 hrs/yr |
| | |
| | CORNERSTONE PERFORMANCE INDICATORS Initiating Events - Unplanned Scrams |
| | - Scrams with Loss of Normal Heat Sink |
| | - Unplanned Power Changes Mitigating Systems - Safety System Functional Failure |
| | - Emergency AC Power System |
| | - High Pressure Injection System |
| | - Heat Removal System |
| | - Residual Heat Removal System |
| | - Cooling Water Systems Barrier Integrity - Reactor Coolant Activity |
| | - Reactor Coolant System Leakage Emergency Preparedness - Drill/Exercise Performance |
| | - ERO Drill Participation |
| | - Alert and Notification System Occupational Radiation - Occupational Exposure Control Safety Public Radiation Safety - RETS/ODCM Radiological Effluent Safeguards - Physical Protection (not publicly available) |
| | |
| | Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Baseline Inspection Performance Indicator Results Results Significance Significance Threshold Threshold Action Matrix NRC Response |
| | |
| | Thresholds Safety Significance Green: Very low safety issue White: Low-to-moderate safety issue Yellow: Substantial safety issue Red: High safety issue NRC Inspection Efforts Green: Only Baseline Inspections White: May increase NRC oversight Yellow: Increased NRC oversight Red: Increased NRC oversight and other NRC actions |
| | |
| | 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 Interaction and Involvement Increasing Regulatory Actions |
| | |
| | National Summary of Nuclear Plant Performance Status at End of CY 2006 Licensee Response 70 Regulatory Response 24 Degraded Cornerstone 6 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total . . . . . . . . . . . . . . . . . .103 |
| | |
| | Catawba CY2006 NRC Inspection Activities |
| *~2400 hours of direct inspection-related activities | | *~2400 hours of direct inspection-related activities |
| *Resident inspector daily inspections | | *Resident inspector daily inspections |
| *Additional baseline inspections conducted by Regional inspectors | | *Additional baseline inspections conducted by Regional inspectors |
| *Resident inspector changes | | *Resident inspector changes |
| *Andy Sabisch promoted to SRI in 9/06 | | *Andy Sabisch promoted to SRI in 9/06 |
| *Gordon Williams assigned as RI in 11/06 Catawba CY2006 Inspection Activities ConductedProblem Identification & Resolution InspectionIndependent Spent Fuel Storage FacilityEmergency PreparednessR.P. Baseline InspectionModifications InspectionIn-service Inspection (U1 & U2)Steam Generator ISI (U1 & U2)Reactor Vessel Head Inspection (U1)Reactor Operator Init ial License ExaminationReactor Operator Requalification Inspection Catawba CY2006 Assessment Results | | *Gordon Williams assigned as RI in 11/06 |
| *Plant performance was within the Licensee Response Column of the NRC'sAction Matrix*All inspection findings were classified as being of very-low safety significance (Green) *All Performance Indicators (PI) were Green Catawba CY2006 Assessment Summary
| |
| *Duke Power Company, LLC operated Catawba in a manner that preserved
| |
|
| |
|
| public health and safety | | Catawba CY2006 Inspection Activities Conducted Problem Identification & Resolution Inspection Independent Spent Fuel Storage Facility Emergency Preparedness R.P. Baseline Inspection Modifications Inspection In-service Inspection (U1 & U2) |
| | Steam Generator ISI (U1 & U2) |
| | Reactor Vessel Head Inspection (U1) |
| | Reactor Operator Initial License Examination Reactor Operator Requalification Inspection |
| | |
| | Catawba CY2006 Assessment Results |
| | * Plant performance was within the Licensee Response Column of the NRCs Action Matrix |
| | * All inspection findings were classified as being of very-low safety significance (Green) |
| | * All Performance Indicators (PI) were Green |
| | |
| | Catawba CY2006 Assessment Summary |
| | *Duke Power Company, LLC operated Catawba in a manner that preserved public health and safety |
| *All cornerstone objectives were met | | *All cornerstone objectives were met |
| *NRC plans to conduct baseline inspections at Catawba for the remainder of CY 2007 with some routine supplemental inspections Catawba CY2007 Scheduled Inspection ActivitiesSecurity Force-on-Force PerformanceComponent Design Basis InspectionISFSI Dry Run & Initial Cask LoadsEmergency PreparednessTriennial Fire Protection InspectionR.P. Baseline InspectionHeat Sink PerformanceInserviceInspection (U2)Containment Sump Modifications (U2)Steam Generator ISI (U2)Reactor Vessel Head Inspection (U2)Reactor Operator Licensing Examinations NRC CY2006 NRC CY2006 Annual Assessment Meeting Annual Assessment Meeting Catawba Nuclear Station Catawba Station Management Response & Remarks Contacting the NRC Report an emergency(301) 816-5100 (call collect) Report a safety concern: (800) 695-7403 Allegation@nrc.gov General information or questionsPublic Web Site: | | *NRC plans to conduct baseline inspections at Catawba for the remainder of CY 2007 with some routine supplemental inspections |
| www.NRC.govSelect "What We Do" for Public Affairs Reference Sources Reactor Oversight Processhttp://www.nrc.gov/NRR/OVERSIGHT/ASSESS/in dex.html Public Electronic Reading Roomhttp://www.nrc.gov/reading-rm.html Public Document Room1-800-397-4209 (Toll Free)}} | | |
| | Catawba CY2007 Scheduled Inspection Activities Security Force-on-Force Performance Component Design Basis Inspection ISFSI Dry Run & Initial Cask Loads Emergency Preparedness Triennial Fire Protection Inspection R.P. Baseline Inspection Heat Sink Performance Inservice Inspection (U2) |
| | Containment Sump Modifications (U2) |
| | Steam Generator ISI (U2) |
| | Reactor Vessel Head Inspection (U2) |
| | Reactor Operator Licensing Examinations |
| | |
| | NRC CY2006 Annual Assessment Meeting Catawba Nuclear Station Catawba Station Management Response & Remarks |
| | |
| | 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 Public Web Site: www.NRC.gov Select What We Do for Public Affairs |
| | |
| | Reference Sources z Reactor Oversight Process http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/in dex.html z Public Electronic Reading Room http://www.nrc.gov/reading-rm.html z Public Document Room 1-800-397-4209 (Toll Free)}} |
|
|---|
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[Table view] |
Text
NRC CY2006 Annual Assessment Meeting Catawba Nuclear Station Rock Hill, SC May 3, 2007
Purpose of Todays Meeting
- Provide a public forum for discussion of Catawba performance
- NRC will address Catawba performance issues identified in the annual assessment letter
- Catawba management 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
Agenda
- Review of Reactor Oversight Process
- National Summary of Plant Performance
- Discussion of Catawba Plant Performance Results
- Catawba Management Response and Remarks
- NRC Available to Address Public Questions
Region II Organization William Travers Regional Administrator Victor McCree Deputy Regional Administrator Charles Casto Joseph Shea Director Division of Reactor Projects Director Division of Reactor Safety Harold Christensen Kriss Kennedy Deputy Director Deputy Director Jim Moorman Regional Specialists Branch Chief Catawba Nuclear Station Project Engineer Andrew Sabisch; SRI Curt Rapp, SPE Gordon Williams, RI Lee Harmon, OA
NRC Performance Goals PRIMARY GOALS Ensure protection of the public health and safety and the environment Ensure the secure use and management of radioactive materials OTHER GOALS
- Ensure openness in NRC regulatory process
- Ensure that NRC actions are effective, efficient, realistic, and timely
- Ensure excellence in NRC management to carry out the NRCs strategic objective
Reactor Oversight Process The NRC monitors plant performance in three major areas:
Reactor Safety (avoiding accidents or transient & reducing their consequences if they occur)
Radiation Safety (both plant workers & the public during routine operations)
Security (protection of the plant against sabotage or other security threats) . . . . .
Major changes in the post-9/11 environment
Reactor Oversight Process Reactor Oversight Process The ROP includes two separate sources of information:
- Inspections conducted by NRC personnel
- Performance Indicators developed from data provided by licensees Inspectors can be Site-based or Region-based Together they provide a composite picture of how the plant is being operated
Examples of Baseline Inspections z Equipment Alignment ~80 hrs/yr z Triennial Fire Protection ~200 hrs every 3 yrs z Operator Response ~125 hrs/yr z Emergency Preparedness ~80 hrs/yr z Rad Release Controls ~110 hrs every 2 yrs z Worker Radiation Protection ~90 hrs/yr z Corrective Action Program ~250 hrs every 2 yrs z Corrective Action Case Reviews ~60 hrs/yr
CORNERSTONE PERFORMANCE INDICATORS Initiating Events - Unplanned Scrams
- Scrams with Loss of Normal Heat Sink
- Unplanned Power Changes Mitigating Systems - Safety System Functional Failure
- Emergency AC Power System
- High Pressure Injection System
- Heat Removal System
- Residual Heat Removal System
- Cooling Water Systems Barrier Integrity - Reactor Coolant Activity
- Reactor Coolant System Leakage Emergency Preparedness - Drill/Exercise Performance
- ERO Drill Participation
- Alert and Notification System Occupational Radiation - Occupational Exposure Control Safety Public Radiation Safety - RETS/ODCM Radiological Effluent Safeguards - Physical Protection (not publicly available)
Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Baseline Inspection Performance Indicator Results Results Significance Significance Threshold Threshold Action Matrix NRC Response
Thresholds Safety Significance Green: Very low safety issue White: Low-to-moderate safety issue Yellow: Substantial safety issue Red: High safety issue NRC Inspection Efforts Green: Only Baseline Inspections White: May increase NRC oversight Yellow: Increased NRC oversight Red: Increased NRC oversight and other NRC actions
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 Interaction and Involvement Increasing Regulatory Actions
National Summary of Nuclear Plant Performance Status at End of CY 2006 Licensee Response 70 Regulatory Response 24 Degraded Cornerstone 6 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total . . . . . . . . . . . . . . . . . .103
Catawba CY2006 NRC Inspection Activities
- ~2400 hours of direct inspection-related activities
- Resident inspector daily inspections
- Additional baseline inspections conducted by Regional inspectors
- Resident inspector changes
- Andy Sabisch promoted to SRI in 9/06
- Gordon Williams assigned as RI in 11/06
Catawba CY2006 Inspection Activities Conducted Problem Identification & Resolution Inspection Independent Spent Fuel Storage Facility Emergency Preparedness R.P. Baseline Inspection Modifications Inspection In-service Inspection (U1 & U2)
Steam Generator ISI (U1 & U2)
Reactor Vessel Head Inspection (U1)
Reactor Operator Initial License Examination Reactor Operator Requalification Inspection
Catawba CY2006 Assessment Results
- Plant performance was within the Licensee Response Column of the NRCs Action Matrix
- All inspection findings were classified as being of very-low safety significance (Green)
- All Performance Indicators (PI) were Green
Catawba CY2006 Assessment Summary
- Duke Power Company, LLC operated Catawba in a manner that preserved public health and safety
- All cornerstone objectives were met
- NRC plans to conduct baseline inspections at Catawba for the remainder of CY 2007 with some routine supplemental inspections
Catawba CY2007 Scheduled Inspection Activities Security Force-on-Force Performance Component Design Basis Inspection ISFSI Dry Run & Initial Cask Loads Emergency Preparedness Triennial Fire Protection Inspection R.P. Baseline Inspection Heat Sink Performance Inservice Inspection (U2)
Containment Sump Modifications (U2)
Steam Generator ISI (U2)
Reactor Vessel Head Inspection (U2)
Reactor Operator Licensing Examinations
NRC CY2006 Annual Assessment Meeting Catawba Nuclear Station Catawba Station Management Response & Remarks
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 Public Web Site: www.NRC.gov Select What We Do for Public Affairs
Reference Sources z Reactor Oversight Process http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/in dex.html z Public Electronic Reading Room http://www.nrc.gov/reading-rm.html z Public Document Room 1-800-397-4209 (Toll Free)
