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| | number = ML081770217 | | | number = ML081770217 |
| | issue date = 06/23/2008 | | | issue date = 06/23/2008 |
| | title = 06/23/2008 Public Meeting Slides, Braidwood Annual Assessment Meeting, Reactor Oversight Program - Cy 2007 | | | title = Public Meeting Slides, Braidwood Annual Assessment Meeting, Reactor Oversight Program - Cy 2007 |
| | author name = | | | author name = |
| | author affiliation = NRC/RGN-III | | | author affiliation = NRC/RGN-III |
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| {{#Wiki_filter:Braidwood Annual Assessment Meeting Braidwood Annual Assessment Meeting Reactor Oversight Program Reactor Oversight Program | | {{#Wiki_filter:Braidwood Annual Assessment Meeting Reactor Oversight Program - CY 2007 Nuclear Regulatory Commission - Region III Braidwood, IL June 23, 2008 |
| --CY 2007 CY 2007 Nuclear Regulatory Commission Nuclear Regulatory Commission
| | |
| --Region III Region III Braidwood, IL Braidwood, IL June 23, 2008 June 23, 2008 Purpose of Today's MeetingPurpose of Today's Meeting To provide a public fo rum for the discussion To provide a public fo rum for the discussion of Braidwood Station's performance of Braidwood Station's performance The NRC will address licensee performance The NRC will address licensee performance issues identified in the annual assessment issues identified in the annual assessment letter letter The Licensee will be provided an opportunity to The Licensee will be provided an opportunity to respond to any information in the letter and respond to any information in the letter and discuss new or existing programs to maintain or discuss new or existing programs to maintain or improve performance improve performance Agenda Agenda Description of NRC Activities Description of NRC Activities IntroductionIntroduction Review of the Reactor Oversight Process (Review of the Reactor Oversight Process (ROP ROP)) National Summary of Plant Performance National Summary of Plant Performance Discussion of Plant Performance Results Discussion of Plant Performance Results Licensee Response and Remarks Licensee Response and RemarksNRC Closing RemarksNRC Closing Remarks Break Break The NRC will be available after the meeting to address The NRC will be available after the meeting to address any public questions any public questions Our Mission Our Mission To license and regulate the To license and regulate the nation's civilian use of nation's civilian use of byproduct, source and special byproduct, source and special nuclear materials to ensure nuclear materials to ensure adequate protection of public adequate protection of public health and safety, promote the health and safety, promote the common defense and security, common defense and security, and protect the environment and protect the environment
| | Purpose of Todays Meeting z To provide a public forum for the discussion of Braidwood Stations performance z The NRC will address licensee performance issues identified in the annual assessment letter z The Licensee will be provided an opportunity to respond to any information in the letter and discuss new or existing programs to maintain or improve performance |
| ..
| | |
| NRC Goals NRC GoalsSafety Safety: Ensure adequate protection of | | Agenda z Description of NRC Activities z Introduction z Review of the Reactor Oversight Process (ROP) z National Summary of Plant Performance z Discussion of Plant Performance Results z Licensee Response and Remarks z NRC Closing Remarks z Break z The NRC will be available after the meeting to address any public questions |
| : Ensure adequate protection of public health and safety and the public health and safety and the environment.
| | |
| environment.Security Security: Ensure adequate protection in
| | Our Mission To license and regulate the nations civilian use of byproduct, source and special nuclear materials to ensure adequate protection of public health and safety, promote the common defense and security, and protect the environment. |
| : Ensure adequate protection in the secure use a nd management of the secure use a nd management of radioactive materials. | | |
| radioactive materials.
| | NRC Goals Safety: Ensure adequate protection of public health and safety and the environment. |
| Some Nuclear Facts Some Nuclear FactsMore than 100 nuclear power plants More than 100 nuclear power plants supply about 20 percent of the supply about 20 percent of the electricity in the U.S. | | Security: Ensure adequate protection in the secure use and management of radioactive materials. |
| electricity in the U.S.Nuclear materials are used in Nuclear materials are used in medicine for cancer treatment and medicine for cancer treatment and diagnosis.diagnosis.Nuclear materials are widely used in Nuclear materials are widely used in industry, such as in density gauges, industry, such as in density gauges, flow measurement devices, flow measurement devices, radiography devices and irradiators.
| | |
| radiography devices and irradiators.
| | Some Nuclear Facts More than 100 nuclear power plants supply about 20 percent of the electricity in the U.S. |
| | Nuclear materials are used in medicine for cancer treatment and diagnosis. |
| | Nuclear materials are widely used in industry, such as in density gauges, flow measurement devices, radiography devices and irradiators. |
| | |
| The NRC Regulates: | | The NRC Regulates: |
| The NRC Regulates:Nuclear reactors Nuclear reactors
| | Nuclear reactors - commercial power reactors, research and test reactors, new reactor designs; Nuclear materials - nuclear reactor fuel, radioactive materials for medical, industrial and academic use; Nuclear waste - transportation, storage and disposal of nuclear material and waste, decommissioning of nuclear facilities; and Nuclear security - physical security of nuclear facilities and materials from sabotage or attacks. |
| --commercial power reactors, research commercial power reactors, research and test reactors, new reactor designs; and test reactors, new reactor designs;Nuclear materials Nuclear materials
| | |
| --nuclear reactor fuel, radioactive nuclear reactor fuel, radioactive materials for medical, industrial and academic use;materials for medical, industrial and academic use;Nuclear wasteNuclear waste
| | What We Dont Do: |
| --transportation, storage and disposal of transportation, storage and disposal of nuclear material and waste, decommissioning of nuclear nuclear material and waste, decommissioning of nuclear facilities; and facilities; andNuclear security Nuclear security
| | Regulate nuclear weapons, military reactors or space vehicle reactors. (These are regulated by other federal agencies.) |
| --physical security of nuclear facilities physical security of nuclear facilities and materials from sabotage or attacks.and materials from sabotage or attacks. | | Own or operate nuclear power plants. |
| What We Don't Do: | | Regulate some radioactive materials, such as naturally occurring radon, X-rays and material produced in particle accelerators. |
| What We Don't Do:Regulate nuclear weapons, military Regulate nuclear weapons, military reactors or space vehicle reactors. (reactors or space vehicle reactors. (These These are regulated by other federal agencies are regulated by other federal agencies
| | (These are regulated by states or other federal agencies.) |
| .).)Own or operate nuclear power plants.
| | |
| Own or operate nuclear power plants.Regulate some radioactive materials, such Regulate some radioactive materials, such as naturally occurring radon, X as naturally occurring radon, X
| | How We Regulate Establish rules and regulations Issue licenses Provide oversight through inspection, enforcement, and evaluation of operational experience Conduct research to provide support for regulatory decisions Respond to events and emergencies |
| --rays and rays and material produced in particle accelerators.
| | |
| material produced in particle accelerators.
| | Assurance of Plant Safety Require defense-in-depth Require long-term maintenance of equipment Require continual training of operators Verify compliance with regulations |
| ((These are regulated by states or other These are regulated by states or other federal agencies federal agencies
| | |
| .).)
| | What We Do - Nuclear Waste The NRC regulates: |
| How We Regulate How We RegulateEstablish rules and regulations Establish rules and regulationsIssue licenses Issue licensesProvide oversight through inspection, Provide oversight through inspection, enforcement, and evaluation of enforcement, and evaluation of operational experience operational experienceConduct research to provide support Conduct research to provide support for regulatory decisions for regulatory decisionsRespond to events and emergencies Respond to events and emergencies Assurance of Plant Safety Assurance of Plant SafetyRequire "defense Require "defense | | * Storage of spent reactor fuel in fuel pools or dry storage casks, and |
| --in in--depth" depth" Require long Require long | | * Any potential national spent fuel storage site. |
| --term maintenance of term maintenance of equipmentequipmentRequire continual training of Require continual training of operators operatorsVerify compliance with regulations Verify compliance with regulations What We Do What We Do
| | |
| --Nuclear Waste Nuclear Waste The NRC regulates The NRC regulates
| | What We Do - Nuclear Security The NRC Requires: |
| ::**Storage of spent Storage of spent reactor fuel in fuel reactor fuel in fuel pools or dry storage pools or dry storage casks, andcasks, and
| | * Well-armed and well-trained security forces, |
| **Any potential Any potential national spent fuel national spent fuel storage site.storage site. | | * Surveillance and perimeter patrols, |
| What We Do What We Do | | * State-of-the-art site access equipment and controls, |
| --Nuclear SecurityNuclear Security The NRC Requires The NRC Requires
| | * Physical barriers and detection zones, and |
| ::**Well Well--armed and wellarmed and well
| | * Intrusion detection systems and alarm stations. |
| --trained security forces,trained security forces,**Surveillance and Surveillance and perimeter patrols, perimeter patrols,**State State--of of--the the--art site art site access equipment and access equipment and controls, controls,**Physical barriers and Physical barriers and detection zones, anddetection zones, and
| | |
| **Intrusion detection Intrusion detection systems and alarm systems and alarm stations.stations.
| | Region III Organization James Caldwell Regional Administrator Mark Satorius Deputy Regional Administrator Cynthia Pederson Steve West Director Division of Reactor Projects (DRP) Director Division of Reactor Safety (DRS) |
| Region III OrganizationJames CaldwellRegional Administrator Mark SatoriusDeputy Regional AdministratorCynthia PedersonDirector Division of Reactor Projects (DRP)Gary ShearDeputy Director Steve WestDirector Division of Reactor Safety (DRS)Anne BolandDeputy DirectorRichard SkokowskiBranch ChiefRegional SpecialistsBraidwoodResident InspectorsBilly DicksonAlex GarmoeProject EngineerReactor EngineerJennifer Dalzell NRC Representatives NRC Representatives Billy Dickson, Senior Resident Inspector Billy Dickson, Senior Resident Inspector | | Gary Shear Anne Boland Deputy Director Deputy Director Richard Skokowski Regional Specialists Branch Chief Braidwood Project Engineer Resident Inspectors Billy Dickson Reactor Engineer Alex Garmoe Jennifer Dalzell |
| --(815) 458 (815) 458--2853 2853 Gregory Roach, Senior Resident Inspector Gregory Roach, Senior Resident Inspector | | |
| --LaSalle LaSalle--(815) 358 (815) 358--8611 8611 Alex Garmoe, Resident Inspector Alex Garmoe, Resident Inspector | | NRC Representatives z Billy Dickson, Senior Resident Inspector |
| --(815) 458 (815) 458--2853 2853 Richard Skokowski, Branch Chief, DRP Richard Skokowski, Branch Chief, DRP
| | - (815) 458-2853 z Gregory Roach, Senior Resident Inspector - LaSalle |
| --(630) 829 (630) 829--9620 9620 Marshall David, Project Manager, NRR Marshall David, Project Manager, NRR | | - (815) 358-8611 z Alex Garmoe, Resident Inspector |
| --(301) 415 (301) 415--1547 1547 NRC RepresentativesNRC Representatives Viktoria Mitlyng, Office of Public Affairs Viktoria Mitlyng, Office of Public Affairs
| | - (815) 458-2853 z Richard Skokowski, Branch Chief, DRP |
| --(630) 829 (630) 829--9662 9662 Prema Chandrathil, Office of Public Affairs Prema Chandrathil, Office of Public Affairs | | - (630) 829-9620 z Marshall David, Project Manager, NRR |
| --(630) 829 (630) 829--9663 9663 Steve Orth, Branch Chief Steve Orth, Branch Chief
| | - (301) 415-1547 |
| --Radiation Radiation Protection Branch, DRS Protection Branch, DRS | | |
| --(630) 829 (630) 829--9827 9827 Stephanie Bush Stephanie Bush | | NRC Representatives z Viktoria Mitlyng, Office of Public Affairs |
| --Goddard, Branch Chief Goddard, Branch Chief
| | - (630) 829-9662 z Prema Chandrathil, Office of Public Affairs |
| --Health Effects Branch, RES Health Effects Branch, RES
| | - (630) 829-9663 z Steve Orth, Branch Chief - Radiation Protection Branch, DRS |
| --(301) 415 (301) 415--6293 6293 Reactor Oversight Process (ROP)Reactor Oversight Process (ROP)SafetyCornerstonesBaseline Inspection ResultsSignificance ThresholdAction MatrixSignificance ThresholdPerformance IndicatorResultsRegulatory ResponseStrategicPerformance AreasSafetyCornerstonesBaseline Inspection ResultsSignificance ThresholdAction MatrixSignificance ThresholdPerformance IndicatorResultsRegulatory ResponseStrategicPerformance Areas Examples of Baseline Inspections Examples of Baseline InspectionsEquipment Alignment Equipment Alignment
| | - (630) 829-9827 z Stephanie Bush-Goddard, Branch Chief - |
| ~80 hrs/yr
| | Health Effects Branch, RES |
| ~80 hrs/yr Triennial Fire Protection Triennial Fire Protection | | - (301) 415-6293 |
| ~250 hrs/3 yrs | | |
| ~250 hrs/3 yrs Operator Response Operator Response
| | Reactor Oversight Process (ROP) |
| ~125 hrs/yr
| | Strategic Performance Areas Safety Cornerstones Baseline Inspection Performance Indicator Results Results Significance Significance Threshold Threshold Action Matrix Regulatory Response |
| ~125 hrs/yr Emergency Preparedness Emergency Preparedness | | |
| ~80 hrs/yr | | Examples of Baseline Inspections z Equipment Alignment ~80 hrs/yr z Triennial Fire Protection ~250 hrs/3 yrs z Operator Response ~125 hrs/yr z Emergency Preparedness ~80 hrs/yr z Radiological Release Controls ~110 hrs/2 yrs z Worker Radiation Protection ~95 hrs/yr z Corrective Action Program ~250 hrs/2 yrs z Corrective Action Reviews ~60 hrs/yr |
| ~80 hrs/yrRadiological Release ControlsRadiological Release Controls
| | |
| ~110 hrs/2 yrs | | Significance Threshold Performance Indicators Green: |
| ~110 hrs/2 yrs Worker Radiation Protection Worker Radiation Protection
| | Green Baseline Inspection only White: |
| ~95 hrs/yr
| | White May increase NRC oversight Yellow: |
| ~95 hrs/yr Corrective Action Program Corrective Action Program | | Yellow Requires more NRC oversight Red: |
| ~250 hrs/2 yrs | | Red Requires more NRC oversight Inspection Findings Green: |
| ~250 hrs/2 yrs Corrective Action Reviews Corrective Action Reviews
| | Green Very low safety significance White: |
| ~60 hrs/yr | | White Low to moderate safety significance Yellow: |
| ~60 hrs/yr Significance Threshold Significance Threshold Performance Indicators Performance Indicators Green Green:Baseline Inspection only White White:May increase NRC oversight Yellow Yellow:Requires more NRC oversightRedRed:Requires more NRC oversightInspection FindingsInspection Findings Green Green:Very low safety significance White White:Low to moderate safety significance Yellow Yellow:Substantial safety significanceRedRed:High safety significance Action Matrix Concept Action Matrix ConceptLicenseeResponseRegulatoryResponseDegradedCornerstoneMultiple/Rep.Degraded CornerstoneUnacceptablePerformance Increasing Safety Significance Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions Increasing Regulatory Actions National Summary of Plant Performance National Summary of Plant PerformanceStatus at End of CY 2007Status at End of CY 2007 Licensee Response Licensee Response 87 87 Regulatory Response Regulatory Response 8 8 Degraded Cornerstone Degraded Cornerstone 8 8 Multiple/Repetitive Degraded Cornerstone Multiple/Repetitive Degraded Cornerstone 1 1 Unacceptable Unacceptable 0 0 Total Total 104 104 National Summary National Summary Performance Indicator Results (End of CY 2007)
| | Yellow Substantial safety significance Red: |
| Performance Indicator Results (End of CY 2007)Green Green 1942 1942White White 8 8YellowYellow 1 1Red Red 0 0 Total Inspection Findings (CY 2007)
| | Red High safety significance |
| Total Inspection Findings (CY 2007)Green Green 759 759White White 9 9YellowYellow 2 2Red Red 0 0 Braidwood Assessment Results Braidwood Assessment Results(Jan 1 -Dec 31, 2007)Safety performance for the last 3 quarters of 2007 Safety performance for the last 3 quarters of 2007 Braidwood Units 1 and 2 were within the Licensee Braidwood Units 1 and 2 were within the Licensee Response column of the NRC Action Matrix. Response column of the NRC Action Matrix. Braidwood Units 1 and 2 were within the Braidwood Units 1 and 2 were within the Regulatory Regulatory Response Response column for the 1 column for the 1 st st quarter of 2007 due to quarter of 2007 due to a White finding in the Public Radiation Safety a White finding in the Public Radiation Safety Cornerstone that occurred in the 1 Cornerstone that occurred in the 1 st st quarter of 2006.
| | |
| quarter of 2006.
| | 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 |
| Safety Significant Findings or PIs Safety Significant Findings or PIs No safety significant findings were No safety significant findings were identified during this assessment period.
| | |
| identified during this assessment period. During the week of January 29, 2007, the During the week of January 29, 2007, the NRC conducted a supplemental inspection NRC conducted a supplemental inspection using Inspection Procedure 95001 for the using Inspection Procedure 95001 for the 1 1 st st quarter 2006 White finding in the Public quarter 2006 White finding in the Public Radiation Safety Cornerstone. No findings Radiation Safety Cornerstone. No findings of significance were identified.
| | National Summary of Plant Performance Status at End of CY 2007 Licensee Response 87 Regulatory Response 8 Degraded Cornerstone 8 Multiple/Repetitive Degraded Cornerstone 1 Unacceptable 0 Total 104 |
| of significance were identified.
| | |
| NRC IP 95001 Evaluation NRC IP 95001 EvaluationInspections encompassed activiti es from the initial response through evaluating Braidwood's root cause evaluation & | | National Summary z Performance Indicator Results (End of CY 2007) |
| corrective actions. Initial ResponseSource of contamination and evaluationStorage of water while repairing the discharge path Review of remediation actions and resumption of liquid releasesIntegrity of blowdown lineIntegrity of modified vacuum breaker valve vaults including leakdetection and alarm system Independent dose calculationIndependent and duplicate analyses of water samples External communications Braidwood Braidwood Inspection Activities Inspection Activities (Jan 1 (Jan 1 --Dec 31, 2007) | | Green 1942 White 8 Yellow 1 Red 0 z Total Inspection Findings (CY 2007) |
| Dec 31, 2007) 12 findings during the assessment period: | | Green 759 White 9 Yellow 2 Red 0 |
| 12 findings during the assessment period:8 in mitigating systems 8 in mitigating systems2 in barrier integrity2 in barrier integrity2 in occupational radiation safety 2 in occupational radiation safety One additional finding was evaluated One additional finding was evaluated separately using the traditional enforcement separately using the traditional enforcement process.process.
| | |
| Braidwood Braidwood Inspection Activities Inspection Activities (Jan 1 (Jan 1 --Dec 31, 2007)Dec 31, 2007) Unit 1: Unit 1: --power operationspower operations | | Braidwood Assessment Results (Jan 1 - Dec 31, 2007) z Safety performance for the last 3 quarters of 2007 Braidwood Units 1 and 2 were within the Licensee Response column of the NRC Action Matrix. |
| --automatic reactor trip due to an offsite grid disturbanceautomatic reactor trip due to an offsite grid disturbance
| | z Braidwood Units 1 and 2 were within the Regulatory Response column for the 1st quarter of 2007 due to a White finding in the Public Radiation Safety Cornerstone that occurred in the 1st quarter of 2006. |
| --refueling outage refueling outage Unit 2: Unit 2:--power operationspower operations | | |
| --manual reactor trip due to a loss of condenser vacuum manual reactor trip due to a loss of condenser vacuum Independent Groundwater Monitoring Activities:Independent Groundwater Monitoring Activities: | | Safety Significant Findings or PIs z No safety significant findings were identified during this assessment period. |
| --Supplemental Inspection 95001 conducted in January 2007Supplemental Inspection 95001 conducted in January 2007
| | z During the week of January 29, 2007, the NRC conducted a supplemental inspection using Inspection Procedure 95001 for the 1st quarter 2006 White finding in the Public Radiation Safety Cornerstone. No findings of significance were identified. |
| --Walkdowns of the Circulating Water blowdown line quarterlyWalkdowns of the Circulating Water blowdown line quarterly
| | |
| --Independent validation of groundwater sample resultsIndependent validation of groundwater sample results Braidwood Annual Assessment Braidwood Annual Assessment Summary Summary (Jan 1 (Jan 1 --Dec 31, 2007)
| | NRC IP 95001 Evaluation Inspections encompassed activities from the initial response through evaluating Braidwoods root cause evaluation & |
| Dec 31, 2007) Exelon Nuclear operated Braidwood Units 1 and 2 Exelon Nuclear operated Braidwood Units 1 and 2 in a manner that preserved public health and safety in a manner that preserved public health and safetyAll cornerstone objectives were met during this All cornerstone objectives were met during this assessment period. | | corrective actions. |
| assessment period.NRC plans to conduct baseline inspections at NRC plans to conduct baseline inspections at Braidwood for the remainder of the current Braidwood for the remainder of the current assessment period.
| | z Initial Response Source of contamination and evaluation Storage of water while repairing the discharge path z Review of remediation actions and resumption of liquid releases Integrity of blowdown line Integrity of modified vacuum breaker valve vaults including leak detection and alarm system z Independent dose calculation z Independent and duplicate analyses of water samples z External communications |
| assessment period. A supplemental 95001 inspection was conducted A supplemental 95001 inspection was conducted during the week of January 29, 2007 with no during the week of January 29, 2007 with no significant findings.
| | |
| significant findings.
| | Braidwood Inspection Activities (Jan 1 - Dec 31, 2007) z 12 findings during the assessment period: |
| Licensee Response and Remarks Licensee Response and Remarks Bryan Hanson Bryan Hanson Site Vice President Site Vice PresidentBraidwood Generating StationBraidwood Generating Station Contacting the NRC Contacting the NRC To Report an emergency To Report an emergency(301) 816 (301) 816--5100 (call collect) 5100 (call collect) To Report a safety concern: | | 8 in mitigating systems 2 in barrier integrity 2 in occupational radiation safety z One additional finding was evaluated separately using the traditional enforcement process. |
| To Report a safety concern: (800) 695 (800) 695--7403 7403Allegation@nrc.gov Allegation@nrc.gov For general information or questions For general information or questionswww.nrc.govwww.nrc.govSelect "Select "What We DoWhat We Do
| | |
| " for Public Affairs
| | Braidwood Inspection Activities (Jan 1 - Dec 31, 2007) z Unit 1: |
| " for Public Affairs Reference Sources Reference Sources Reactor Oversight Process Reactor Oversight Processhttp://www.nrc.gov/NRR
| | - power operations |
| /OVERSIGHT/ASSESS/index.http://www.nrc.gov/NRR
| | - automatic reactor trip due to an offsite grid disturbance |
| /OVERSIGHT/ASSESS/index. | | - refueling outage z Unit 2: |
| html html Public Electronic Reading Room Public Electronic Reading Roomhttp://www.nrc.gov/readinghttp://www.nrc.gov/reading | | - power operations |
| --rm.html rm.html Public Document Room Public Document Room1 1--800 800--397 397--4209 (Toll Free) 4209 (Toll Free)}}
| | - manual reactor trip due to a loss of condenser vacuum z Independent Groundwater Monitoring Activities: |
| | - Supplemental Inspection 95001 conducted in January 2007 |
| | - Walkdowns of the Circulating Water blowdown line quarterly |
| | - Independent validation of groundwater sample results |
| | |
| | Braidwood Annual Assessment Summary (Jan 1 - Dec 31, 2007) z Exelon Nuclear operated Braidwood Units 1 and 2 in a manner that preserved public health and safety z All cornerstone objectives were met during this assessment period. |
| | z NRC plans to conduct baseline inspections at Braidwood for the remainder of the current assessment period. |
| | z A supplemental 95001 inspection was conducted during the week of January 29, 2007 with no significant findings. |
| | |
| | Licensee Response and Remarks Bryan Hanson Site Vice President Braidwood Generating Station |
| | |
| | Contacting the NRC z To Report an emergency (301) 816-5100 (call collect) z To Report a safety concern: |
| | (800) 695-7403 Allegation@nrc.gov z For general information or questions www.nrc.gov Select What We Do for Public Affairs |
| | |
| | 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)}} |
|
|---|
Category:Meeting Briefing Package/Handouts
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Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2
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Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041)
ML24060A1692024-03-0707 March 2024
NRC Slides for March 7, 2024 Regulatory Conference with Constellation Nuclear Regarding Braidwood
BW240007, Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations2024-02-29029 February 2024
Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations
ML24057A3032024-02-26026 February 2024
Attachment 1: Braidwood Station Regulatory Conference Information
ML24057A3062024-02-24024 February 2024
Attachment 4: BW-SDP-006 Rev. 0 - Braidwood 2B AF Pump Fuel Oil Leak SOP Sensitivities
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
ML24057A3042024-01-22022 January 2024
Attachment 2: EC 640630 Rev. 000 - Documentation of Test Results with Diluted Lube Oil from Fuel In-Leakage - 28 AF Diesel Engine Past Operability
ML24003A1812024-01-0808 January 2024
Handout - Byron-Braidwood Core Monitoring and Support System LAR Pre-Submittal Meeting January 8,2024
ML24057A3052023-12-12012 December 2023
Attachment 3: EC 640287 Rev. 000 - Past Operability Test Plan Acceptance Related to 2AF01PB-K
ML23345A0362023-12-11011 December 2023
ATWS Uet December 11, 2023 Pre-submittal Meeting Slides
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)
ML23272A0622023-09-29029 September 2023
Ultimate Heat Sink Temperature Tech Spec Limit Change
ML23255A1042023-08-11011 August 2023
Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout
ML23163A1642023-06-12012 June 2023
2022 Braidwood/Byron End-of-Cycle Meeting Presentation
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)
ML22159A3332022-06-0909 June 2022
Presentation Slides for Braidwood and Byron 2021 End of Cycle Meeting
ML21320A0672021-11-17017 November 2021
NRC Pre-Submittal Meeting - Braidwood, Unit 2, LAR for Removal of Unit 2 License Condition for Closure Stud Hole Location No. 35 (EPID L-2021-LRM-0089) (Slides)
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
ML21166A3722021-06-15015 June 2021
End-of-Cycle Meeting Presentation
ML21130A6252021-05-12012 May 2021
NRC Pre-Submittal Meeting - Braidwood LAR for Ultimate Heat Sink (EPID L-2021-LRM-0040) (Slides)
ML21078A0952021-03-0808 March 2021
Session W20 - James Petty - Slide Deck 3
ML20261G7322020-09-16016 September 2020
Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a
ML20209A5322020-07-24024 July 2020
2019 Braidwood and Byron End-of-Cycle Presentation
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
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
ML20091L0432020-04-0101 April 2020
Public Meeting Handout for Braidwood, Unit 2, April 1, 2020
ML19318F9512019-11-20020 November 2019
Presentation Slides for November 20, 2019, Pre-Application Meeting - Request for Revision to Quality Assurance Program Internal Audit Frequency
ML19317C9952019-11-12012 November 2019
In-Service Testing Supplemental Position Indication Relief Request NRC Pre-Application Meeting November 18, 2019
ML19161A2572019-06-0404 June 2019
BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019
ML19151A6602019-05-31031 May 2019
BWR Fleet Mssv/Srv Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019
ML19022A2002019-01-23023 January 2019
Request for Use of ASME Code Case N-879 for Exelon Nuclear Power Plants
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
ML18218A1122018-08-0808 August 2018
Reactor Pressure Vessel Head Penetration Nozzle Post Peening Follow-up Inspection Relief Requests for Byron Unit 2 and Braidwood Unit 1
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
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Summary of December 17, 2017, Closed Meeting with Exelon Generation Company, LLC, Regarding Tvel Lead Test Assemblies to Be Placed in the Braidwood Reactor (EPID 000976/05000456/L-2017-LRM and 000976/05000457/L-2017-LRM-0047
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OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns
ML17132A1772017-05-25025 May 2017
LAR for Control Room Cooling at Byron and Braidwood Stations
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Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards
ML16075A3292016-03-16016 March 2016
OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations
ML16062A4222016-03-0202 March 2016
Meeting Slides for March 7, 2016 Public Meeting to Discuss Backfit Appeal
ML15232A6832015-08-27027 August 2015
Stations Auxiliary Feedwater System - Unit Cross-tie License Amendment Request
ML15209A9722015-07-30030 July 2015
Alloy 600 PWSCC Mitigation Plan for Reactor Vessel Head Penetration Nozzles Utilizing Cavitation Peening at Byron and Braidwood
ML15133A4732015-05-20020 May 2015
Digital Upgrades of the Non-Safety Related NSSS Control Systems at Byron and Braidwood Stations
2024-04-09
[Table view]
Category:Slides and Viewgraphs
MONTHYEARML24310A0672024-11-0505 November 2024
Constellation NRC Pre-Submittal Meeting Slides - Proposed Alternative for Reactor Vessel Closure Stud Exam Optimization
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Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2
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Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041)
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NRC Slides for March 7, 2024 Regulatory Conference with Constellation Nuclear Regarding Braidwood
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Attachment 1: Braidwood Station Regulatory Conference Information
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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
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Handout - Byron-Braidwood Core Monitoring and Support System LAR Pre-Submittal Meeting January 8,2024
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ATWS Uet December 11, 2023 Pre-submittal Meeting Slides
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NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides)
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Ultimate Heat Sink Temperature Tech Spec Limit Change
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Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout
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2022 Braidwood/Byron End-of-Cycle Meeting Presentation
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Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides
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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
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Public Call with Constellation January 30, 2023 (Slides)
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Presentation Slides for Braidwood and Byron 2021 End of Cycle Meeting
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Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval
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End-of-Cycle Meeting Presentation
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BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs
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NRC Pre-Submittal Meeting - Braidwood LAR for Ultimate Heat Sink (EPID L-2021-LRM-0040) (Slides)
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Session W20 - James Petty - Slide Deck 3
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2019 Braidwood and Byron End-of-Cycle Presentation
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NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response
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Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach
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NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections
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Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1)
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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
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LAR for Control Room Cooling at Byron and Braidwood Stations
ML16077A1562016-03-22022 March 2016
Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards
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Meeting Slides for March 7, 2016 Public Meeting to Discuss Backfit Appeal
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Stations Auxiliary Feedwater System - Unit Cross-tie License Amendment Request
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Alloy 600 PWSCC Mitigation Plan for Reactor Vessel Head Penetration Nozzles Utilizing Cavitation Peening at Byron and Braidwood
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Bb Station Requests for Relief for Alternate Examination Frequency
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EPRI Tech Basis for Brd-Byr Head RR
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Digital Upgrades of the Non-Safety Related NSSS Control Systems at Byron and Braidwood Stations
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Preliminary Site-Specific Results of the Environmental Review for Braidwood Station License Renewal
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Byron/Braidwood Auxiliary Feedwater Cross-Tie
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2024-04-09
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Text
Braidwood Annual Assessment Meeting Reactor Oversight Program - CY 2007 Nuclear Regulatory Commission - Region III Braidwood, IL June 23, 2008
Purpose of Todays Meeting z To provide a public forum for the discussion of Braidwood Stations performance z The NRC will address licensee performance issues identified in the annual assessment letter z The Licensee will be provided an opportunity to respond to any information in the letter and discuss new or existing programs to maintain or improve performance
Agenda z Description of NRC Activities z Introduction z Review of the Reactor Oversight Process (ROP) z National Summary of Plant Performance z Discussion of Plant Performance Results z Licensee Response and Remarks z NRC Closing Remarks z Break z The NRC will be available after the meeting to address any public questions
Our Mission To license and regulate the nations civilian use of byproduct, source and special nuclear materials to ensure adequate protection of public health and safety, promote the common defense and security, and protect the environment.
NRC Goals Safety: Ensure adequate protection of public health and safety and the environment.
Security: Ensure adequate protection in the secure use and management of radioactive materials.
Some Nuclear Facts More than 100 nuclear power plants supply about 20 percent of the electricity in the U.S.
Nuclear materials are used in medicine for cancer treatment and diagnosis.
Nuclear materials are widely used in industry, such as in density gauges, flow measurement devices, radiography devices and irradiators.
The NRC Regulates:
Nuclear reactors - commercial power reactors, research and test reactors, new reactor designs; Nuclear materials - nuclear reactor fuel, radioactive materials for medical, industrial and academic use; Nuclear waste - transportation, storage and disposal of nuclear material and waste, decommissioning of nuclear facilities; and Nuclear security - physical security of nuclear facilities and materials from sabotage or attacks.
What We Dont Do:
Regulate nuclear weapons, military reactors or space vehicle reactors. (These are regulated by other federal agencies.)
Own or operate nuclear power plants.
Regulate some radioactive materials, such as naturally occurring radon, X-rays and material produced in particle accelerators.
(These are regulated by states or other federal agencies.)
How We Regulate Establish rules and regulations Issue licenses Provide oversight through inspection, enforcement, and evaluation of operational experience Conduct research to provide support for regulatory decisions Respond to events and emergencies
Assurance of Plant Safety Require defense-in-depth Require long-term maintenance of equipment Require continual training of operators Verify compliance with regulations
What We Do - Nuclear Waste The NRC regulates:
- Storage of spent reactor fuel in fuel pools or dry storage casks, and
- Any potential national spent fuel storage site.
What We Do - Nuclear Security The NRC Requires:
- Well-armed and well-trained security forces,
- Surveillance and perimeter patrols,
- State-of-the-art site access equipment and controls,
- Physical barriers and detection zones, and
- Intrusion detection systems and alarm stations.
Region III Organization James Caldwell Regional Administrator Mark Satorius Deputy Regional Administrator Cynthia Pederson Steve West Director Division of Reactor Projects (DRP) Director Division of Reactor Safety (DRS)
Gary Shear Anne Boland Deputy Director Deputy Director Richard Skokowski Regional Specialists Branch Chief Braidwood Project Engineer Resident Inspectors Billy Dickson Reactor Engineer Alex Garmoe Jennifer Dalzell
NRC Representatives z Billy Dickson, Senior Resident Inspector
- (815) 458-2853 z Gregory Roach, Senior Resident Inspector - LaSalle
- (815) 358-8611 z Alex Garmoe, Resident Inspector
- (815) 458-2853 z Richard Skokowski, Branch Chief, DRP
- (630) 829-9620 z Marshall David, Project Manager, NRR
- (301) 415-1547
NRC Representatives z Viktoria Mitlyng, Office of Public Affairs
- (630) 829-9662 z Prema Chandrathil, Office of Public Affairs
- (630) 829-9663 z Steve Orth, Branch Chief - Radiation Protection Branch, DRS
- (630) 829-9827 z Stephanie Bush-Goddard, Branch Chief -
Health Effects Branch, RES
- (301) 415-6293
Reactor Oversight Process (ROP)
Strategic Performance Areas Safety Cornerstones Baseline Inspection Performance Indicator Results Results Significance Significance Threshold Threshold Action Matrix Regulatory Response
Examples of Baseline Inspections z Equipment Alignment ~80 hrs/yr z Triennial Fire Protection ~250 hrs/3 yrs z Operator Response ~125 hrs/yr z Emergency Preparedness ~80 hrs/yr z Radiological Release Controls ~110 hrs/2 yrs z Worker Radiation Protection ~95 hrs/yr z Corrective Action Program ~250 hrs/2 yrs z Corrective Action Reviews ~60 hrs/yr
Significance Threshold Performance Indicators Green:
Green Baseline Inspection only White:
White May increase NRC oversight Yellow:
Yellow Requires more NRC oversight Red:
Red Requires more NRC oversight Inspection Findings Green:
Green Very low safety significance White:
White Low to moderate safety significance Yellow:
Yellow Substantial safety significance Red:
Red High safety significance
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
National Summary of Plant Performance Status at End of CY 2007 Licensee Response 87 Regulatory Response 8 Degraded Cornerstone 8 Multiple/Repetitive Degraded Cornerstone 1 Unacceptable 0 Total 104
National Summary z Performance Indicator Results (End of CY 2007)
Green 1942 White 8 Yellow 1 Red 0 z Total Inspection Findings (CY 2007)
Green 759 White 9 Yellow 2 Red 0
Braidwood Assessment Results (Jan 1 - Dec 31, 2007) z Safety performance for the last 3 quarters of 2007 Braidwood Units 1 and 2 were within the Licensee Response column of the NRC Action Matrix.
z Braidwood Units 1 and 2 were within the Regulatory Response column for the 1st quarter of 2007 due to a White finding in the Public Radiation Safety Cornerstone that occurred in the 1st quarter of 2006.
Safety Significant Findings or PIs z No safety significant findings were identified during this assessment period.
z During the week of January 29, 2007, the NRC conducted a supplemental inspection using Inspection Procedure 95001 for the 1st quarter 2006 White finding in the Public Radiation Safety Cornerstone. No findings of significance were identified.
NRC IP 95001 Evaluation Inspections encompassed activities from the initial response through evaluating Braidwoods root cause evaluation &
corrective actions.
z Initial Response Source of contamination and evaluation Storage of water while repairing the discharge path z Review of remediation actions and resumption of liquid releases Integrity of blowdown line Integrity of modified vacuum breaker valve vaults including leak detection and alarm system z Independent dose calculation z Independent and duplicate analyses of water samples z External communications
Braidwood Inspection Activities (Jan 1 - Dec 31, 2007) z 12 findings during the assessment period:
8 in mitigating systems 2 in barrier integrity 2 in occupational radiation safety z One additional finding was evaluated separately using the traditional enforcement process.
Braidwood Inspection Activities (Jan 1 - Dec 31, 2007) z Unit 1:
- power operations
- automatic reactor trip due to an offsite grid disturbance
- refueling outage z Unit 2:
- power operations
- manual reactor trip due to a loss of condenser vacuum z Independent Groundwater Monitoring Activities:
- Supplemental Inspection 95001 conducted in January 2007
- Walkdowns of the Circulating Water blowdown line quarterly
- Independent validation of groundwater sample results
Braidwood Annual Assessment Summary (Jan 1 - Dec 31, 2007) z Exelon Nuclear operated Braidwood Units 1 and 2 in a manner that preserved public health and safety z All cornerstone objectives were met during this assessment period.
z NRC plans to conduct baseline inspections at Braidwood for the remainder of the current assessment period.
z A supplemental 95001 inspection was conducted during the week of January 29, 2007 with no significant findings.
Licensee Response and Remarks Bryan Hanson Site Vice President Braidwood Generating Station
Contacting the NRC z To Report an emergency (301) 816-5100 (call collect) z To Report a safety concern:
(800) 695-7403 Allegation@nrc.gov z For general information or questions www.nrc.gov Select What We Do for Public Affairs
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)
