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| {{#Wiki_filter:NRC & NEAC Meeting NRC & NEAC Meeting Concerning Millstone Station PerformanceConcerning Millstone Station PerformanceReactor Oversight Program Reactor Oversight Program | | {{#Wiki_filter:NRC & NEAC Meeting Concerning Millstone Station Performance Reactor Oversight Program - CY 2005 Nuclear Regulatory Commission - Region I King of Prussia, Pennsylvania March 29, 2006 |
| --CY 2005CY 2005Nuclear Regulatory Commission Nuclear Regulatory Commission
| |
| --Region IRegion IKing of Prussia, PennsylvaniaKing of Prussia, PennsylvaniaMarch 29, 2006March 29, 2006 Purpose of Today's MeetingPurpose of Today's MeetingA public forum for discussion of Millstone Station's A public forum for discussion of Millstone Station's annual performance for CY 2005annual performance for CY 2005NRC will address Millstone Station's performance NRC will address Millstone Station's performance as discussed in the NRC annual assessment letter to as discussed in the NRC annual assessment letter to Dominion Nuclear Connecticut, Inc.Dominion Nuclear Connecticut, Inc.NEAC will be given the opportunity to respond to NEAC will be given the opportunity to respond to the information, request clarifications, and ask the information, request clarifications, and ask additional questions as neededadditional questions as needed AgendaAgendaIntroduction Introduction Review of Reactor Oversight ProcessReview of Reactor Oversight ProcessNational Summary of Plant PerformanceNational Summary of Plant PerformanceDiscussion of Millstone Station Performance ResultsDiscussion of Millstone Station Performance ResultsNEAC Response and RemarksNEAC Response and RemarksNRC and NEAC Closing RemarksNRC and NEAC Closing RemarksBreakBreakNRC available for public questionsNRC available for public questionsand commentsand comments Region I OrganizationRegion I OrganizationSamuel J. CollinsRegional AdministratorMarc L. DapasDeputy Regional AdministratorBrian E. HolianDirector Division of Reactor ProjectsDavid C. LewDeputy DirectorA. Randolph BloughDirector Division of Reactor SafetyMarsha K. GamberoniDeputy DirectorPaul G. KrohnBranch ChiefRegional SpecialistsMillstoneResident InspectorsMax SchneiderJamie BenjaminSilas KennedySenior Project EngineersScott BarberBarry Norris NRC RepresentativesNRC RepresentativesDavid C. Lew, Deputy Division Director, DRPDavid C. Lew, Deputy Division Director, DRP
| |
| --(610) 337 (610) 337--52295229Max Schneider, Senior Resident InspectorMax Schneider, Senior Resident InspectorJamie Benjamin, Resident InspectorJamie Benjamin, Resident InspectorSilas Kennedy, Resident InspectorSilas Kennedy, Resident Inspector
| |
| --(860) 447 (860) 447--31703170Paul Krohn, Branch ChiefPaul Krohn, Branch Chief
| |
| --(610) 337 (610) 337--51205120Scott Barber, Senior Project EngineerScott Barber, Senior Project Engineer
| |
| --(610) 337(610) 337--52325232 NRC Performance Goals NRC Performance GoalsSafety: Ensure protection of the public health and Safety: Ensure protection of the public health and safety and the environmentsafety and the environmentSecurity: Ensure the secure use and management of Security: Ensure the secure use and management of radioactive materialsradioactive materialsOpenness: Ensure openness in our regulatory processOpenness: Ensure openness in our regulatory processEffectiveness: Ensure that NRC actions are effective, Effectiveness: Ensure that NRC actions are effective, efficient, realistic, and timelyefficient, realistic, and timelyManagement: Ensure excellence in agency Management: Ensure excellence in agency management to carry out the NRC strategic objectivemanagement to carry out the NRC strategic objective Reactor Oversight ProcessReactor Oversight ProcessSafetyCornerstonesBaseline Inspection ResultsSignificance ThresholdAction MatrixSignificance ThresholdPerformance IndicatorResultsRegulatory ResponseStrategicPerformance AreasSafetyCornerstonesBaseline Inspection ResultsSignificance ThresholdAction MatrixSignificance ThresholdPerformance IndicatorResultsRegulatory ResponseStrategicPerformance Areas Examples of Baseline InspectionsExamples of Baseline InspectionsEquipment Alignment Equipment Alignment ~80 hrs/yr~80 hrs/yrTriennial Fire Protection Triennial Fire Protection ~200 hrs every 3 yrs~200 hrs every 3 yrsOperator Response Operator Response ~125 hrs/yr~125 hrs/yrEmergency Preparedness Emergency Preparedness ~80 hrs/yr~80 hrs/yr Rad RadRelease Controls Release Controls ~110 hrs every 2 yrs~110 hrs every 2 yrsWorker Radiation Protection Worker Radiation Protection ~90 hrs/yr~90 hrs/yrCorrective Action Program Corrective Action Program ~250 hrs every 2 yrs~250 hrs every 2 yrsCorrective Action Case Reviews Corrective Action Case Reviews ~60 hrs/yr~60 hrs/yr Significance ThresholdSignificance ThresholdPerformance IndicatorsPerformance IndicatorsGreenGreen::Baseline InspectionBaseline Inspection White White::May increase NRC oversightMay increase NRC oversightYellowYellow::Requires more NRC oversightRequires more NRC oversight Red Red::Requires more NRC oversightRequires more NRC oversightInspection FindingsInspection FindingsGreenGreen::Very low safety issueVery low safety issue White White::Low to moderate safety issueLow to moderate safety issueYellowYellow::Substantial safety issueSubstantial safety issue Red Red::High safety issueHigh safety issue Action Matrix ConceptAction Matrix ConceptLicenseeResponseRegulatoryResponseDegradedCornerstoneMultiple/Rep.DegradedCornerstoneUnacceptablePerformanceIncreasing Safety SignificanceIncreasing Safety SignificanceIncreasing NRC Inspection EffortsIncreasing NRC Inspection EffortsIncreasing NRC/Licensee Management InvolvementIncreasing NRC/Licensee Management InvolvementIncreasing Regulatory ActionsIncreasing Regulatory Actions National Summary of Plant PerformanceNational Summary of Plant PerformanceStatus at End of CY 2005Status at End of CY 2005Licensee Response Licensee Response 84 84Regulatory Response Regulatory Response 12 12Degraded Cornerstone Degraded Cornerstone 4 4Multiple/Repetitive Degraded CornerstoneMultiple/Repetitive Degraded Cornerstone 3 3Unacceptable Unacceptable 0 0TotalTotal 103 103 National Summary National SummaryPerformance Indicator Results (at end of CY 2005)Performance Indicator Results (at end of CY 2005)GreenGreen18501850 White White 4 4YellowYellow 0 0 Red Red 0 0Total Inspection Findings (CY 2005)Total Inspection Findings (CY 2005)GreenGreen849849 White White 10 10YellowYellow 1 1 Red Red 0 0 Millstone Assessment Results Millstone Assessment Results (Jan. 1 (Jan. 1 --Dec. 31, 2005)
| |
| Dec. 31, 2005)Licensee Response ColumnLicensee Response ColumnNo safety significant findings or PIsNo safety significant findings or PIs Millstone Inspection Activities(Jan. 1 (Jan. 1 --Dec. 31, 2005)
| |
| Dec. 31, 2005)Hours of inspection related activitiesHours of inspection related activities
| |
| --5021 hours at Millstone Unit 25021 hours at Millstone Unit 2
| |
| --6115 hours at Millstone Unit 36115 hours at Millstone Unit 3Three resident inspectors assigned to the siteThree resident inspectors assigned to the site
| |
| --Jamie Benjamin started at Millstone in June 2005Jamie Benjamin started at Millstone in June 2005InspectionsInspections 2 2 2 2Unit 3 only 0 0 7 7Unit 2 only 1 1 5 5Units 2 & 3 Team TeamRegionalRegional Millstone Inspection ActivitiesMillstone Inspection Activities(Jan. 1 (Jan. 1 --Dec. 31, 2005)
| |
| Dec. 31, 2005)Inspection findingsInspection findings
| |
| --3 findings of very low safety significance (Green) at Unit 23 findings of very low safety significance (Green) at Unit 2
| |
| --12 findings of very low safety significance (Green) at Unit 312 findings of very low safety significance (Green) at Unit 3
| |
| --2 findings of very low safety significance (Green) common2 findings of very low safety significance (Green) commonto both unitsto both unitsUnit 3 refueling outage Unit 3 refueling outage (09/29 (09/29 --10/27/05)10/27/05)--no findings related to the outageno findings related to the outage Millstone Inspection ActivitiesMillstone Inspection Activities(Jan. 1 (Jan. 1 --Dec. 31, 2005)Dec. 31, 2005)Unit 2 Triennial Fire Protection team inspectionUnit 2 Triennial Fire Protection team inspection
| |
| --no findingsno findingsUnit 2 reactor head replacement inspectionUnit 2 reactor head replacement inspection
| |
| --no findingsno findingsUnit 3 safety system design team inspectionUnit 3 safety system design team inspection
| |
| --no findingsno findingsUnit 3 Special Inspection TeamUnit 3 Special Inspection Team
| |
| --6 findings of very low safety significance (Green)6 findings of very low safety significance (Green)
| |
| Millstone Millstone Annual Assessment SummaryAnnual Assessment Summary(Jan. 1 (Jan. 1 --Dec. 31, 2005)Dec. 31, 2005)Dominion operated Millstone Units 2 & 3 in a manner Dominion operated Millstone Units 2 & 3 in a manner that preserved public health and safetythat preserved public health and safetyAll cornerstone objectives were metAll cornerstone objectives were metNRC plans baseline inspections at Millstone for the NRC plans baseline inspections at Millstone for the remainder of the assessment periodremainder of the assessment period Contacting the NRCContacting the NRCReport an emergencyReport an emergency(301) 816(301) 816--5100 (call collect)5100 (call collect)Report a safety concern: Report a safety concern: (800) 695(800) 695--7403 7403 Allegation@nrc.govAllegation@nrc.govGeneral information or questionsGeneral information or questionswww.nrc.govwww.nrc.govSelect "What We Do" for Public AffairsSelect "What We Do" for Public Affairs Paul Paul KrohnKrohn, Branch Chief, Branch Chiefpgk1@nrc.govpgk1@nrc.gov Reference SourcesReference SourcesReactor Oversight ProcessReactor Oversight Processhttp://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.htmlhttp://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.htmlPublic Electronic Reading RoomPublic Electronic Reading Roomhttp://www.nrc.gov/readinghttp://www.nrc.gov/reading
| |
| --rm.htmlrm.htmlPublic Document RoomPublic Document Room 1 1--800 800--397 397--4209 (Toll Free)4209 (Toll Free)
| |
| NEAC Response and RemarksNEAC Response and RemarksMillstone Nuclear Power StationMillstone Nuclear Power Station Unit 2 and Unit 3 Unit 2 and Unit 3 END OF THE PRESENTATIONEND OF THE PRESENTATIONNuclear Regulatory Commission Nuclear Regulatory Commission
| |
| --Region IRegion IKing of Prussia, PennsylvaniaKing of Prussia, PennsylvaniaMarch 29, 2006March 29, 2006 Potential Public Interest IssuesPotential Public Interest IssuesSafety Concerns Brought to the NRCSafety Concerns Brought to the NRCNRC has a formal processNRC has a formal processConcerns are reviewed on an individual basis by NRC technical, Concerns are reviewed on an individual basis by NRC technical, legal, investigative staff and managementlegal, investigative staff and managementIssues of immediate concern receive prompt attention by NRC and Issues of immediate concern receive prompt attention by NRC and by nuclear power plant managementby nuclear power plant managementNRC'sNRC'sprocess requires reviews of all valid safety issues to ensure process requires reviews of all valid safety issues to ensure they are adequately addressedthey are adequately addressedNRC implements measures to protect the identity of allegers NRC implements measures to protect the identity of allegers including not commenting on the existence of a specific allegatiincluding not commenting on the existence of a specific allegati on on Potential Public Interest IssuesPotential Public Interest IssuesRecent Press Articles on Security IssuesRecent Press Articles on Security IssuesCurrent NRC policy is to not discuss security matters in a Current NRC policy is to not discuss security matters in a public forumpublic forumNRC will not comment on existence of allegations in this NRC will not comment on existence of allegations in this area areaNotwithstanding these policies, we want to assure the Notwithstanding these policies, we want to assure the public that if safety issues did exist, the NRC would take public that if safety issues did exist, the NRC would take prompt action to address themprompt action to address them Potential Public Interest IssuesPotential Public Interest IssuesStrontiumStrontium--90 (SR 90 (SR--90)90)Fission process byproduct (29 year halfFission process byproduct (29 year half
| |
| --life)life)Potential sources in the EnvironmentPotential sources in the Environment
| |
| --16,800,000 curies 16,800,000 curies
| |
| --nuclear weapons testing (UNSCEAR 2001)nuclear weapons testing (UNSCEAR 2001)
| |
| --212,000 curies 212,000 curies
| |
| --1986 Chernobyl accident (UNSCEAR 2001)1986 Chernobyl accident (UNSCEAR 2001)
| |
| --0.00012 to 0.001 curies 0.00012 to 0.001 curies
| |
| --from all 103 operating nuclear from all 103 operating nuclear power plants power plantsFor nuclear reactor releases, SRFor nuclear reactor releases, SR
| |
| --89 (50 day half89 (50 day half
| |
| --life) is life) is always present with SRalways present with SR
| |
| --90 90 Potential Public Interest IssuesPotential Public Interest IssuesStrontiumStrontium--90 (SR 90 (SR--90) continued90) continued Mid 1990's Mid 1990's
| |
| --Release levels of SRRelease levels of SR
| |
| --90 were so low that nuclear 90 were so low that nuclear utilities had difficulty measuring the amounts releasedutilities had difficulty measuring the amounts releasedNRC allowed SRNRC allowed SR
| |
| --90 monitoring by using goat milk samples90 monitoring by using goat milk samplesGoat milk samples indicated low levels of SRGoat milk samples indicated low levels of SR
| |
| --90 without the 90 without the presence of SRpresence of SR
| |
| --89 (indicating not originating from a nuclear 89 (indicating not originating from a nuclear power plant) power plant)Most likely source is from 1950's and 1960's atmospheric Most likely source is from 1950's and 1960's atmospheric nuclear weapons testingnuclear weapons testing Potential Public Interest IssuesPotential Public Interest IssuesNatural
| |
|
| |
|
| ==Background:==
| | Purpose of Todays Meeting A public forum for discussion of Millstone Stations annual performance for CY 2005 NRC will address Millstone Stations performance as discussed in the NRC annual assessment letter to Dominion Nuclear Connecticut, Inc. |
| Natural | | NEAC will be given the opportunity to respond to the information, request clarifications, and ask additional questions as needed |
| | |
| | Agenda z Introduction z Review of Reactor Oversight Process z National Summary of Plant Performance z Discussion of Millstone Station Performance Results z NEAC Response and Remarks z NRC and NEAC Closing Remarks z Break z NRC available for public questions and comments |
| | |
| | Region I Organization Samuel J. Collins Regional Administrator Marc L. Dapas Deputy Regional Administrator Brian E. Holian A. Randolph Blough Director Division of Reactor Projects Director Division of Reactor Safety David C. Lew Marsha K. Gamberoni Deputy Director Deputy Director Paul G. Krohn Regional Specialists Branch Chief Millstone Senior Project Engineers Resident Inspectors Scott Barber Max Schneider Barry Norris Jamie Benjamin Silas Kennedy |
| | |
| | NRC Representatives z David C. Lew, Deputy Division Director, DRP |
| | - (610) 337-5229 z Max Schneider, Senior Resident Inspector z Jamie Benjamin, Resident Inspector z Silas Kennedy, Resident Inspector |
| | - (860) 447-3170 z Paul Krohn, Branch Chief |
| | - (610) 337-5120 z Scott Barber, Senior Project Engineer |
| | - (610) 337-5232 |
| | |
| | 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 NRC strategic objective |
| | |
| | Reactor Oversight Process 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 ~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 |
| | |
| | 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 |
| | |
| | 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 2005 Licensee Response 84 Regulatory Response 12 Degraded Cornerstone 4 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total 103 |
| | |
| | National Summary z Performance Indicator Results (at end of CY 2005) |
| | Green 1850 White 4 Yellow 0 Red 0 z Total Inspection Findings (CY 2005) |
| | Green 849 White 10 Yellow 1 Red 0 |
| | |
| | Millstone Assessment Results (Jan. 1 - Dec. 31, 2005) z Licensee Response Column z No safety significant findings or PIs |
| | |
| | Millstone Inspection Activities (Jan. 1 - Dec. 31, 2005) |
| | Hours of inspection related activities |
| | - 5021 hours at Millstone Unit 2 |
| | - 6115 hours at Millstone Unit 3 Three resident inspectors assigned to the site |
| | - Jamie Benjamin started at Millstone in June 2005 Inspections Regional Team Units 2 & 3 5 1 Unit 2 only 7 0 Unit 3 only 2 2 |
| | |
| | Millstone Inspection Activities (Jan. 1 - Dec. 31, 2005) |
| | Inspection findings |
| | - 3 findings of very low safety significance (Green) at Unit 2 |
| | - 12 findings of very low safety significance (Green) at Unit 3 |
| | - 2 findings of very low safety significance (Green) common to both units Unit 3 refueling outage (09/29 - 10/27/05) |
| | - no findings related to the outage |
| | |
| | Millstone Inspection Activities (Jan. 1 - Dec. 31, 2005) |
| | Unit 2 Triennial Fire Protection team inspection |
| | - no findings Unit 2 reactor head replacement inspection |
| | - no findings Unit 3 safety system design team inspection |
| | - no findings Unit 3 Special Inspection Team |
| | - 6 findings of very low safety significance (Green) |
| | |
| | Millstone Annual Assessment Summary (Jan. 1 - Dec. 31, 2005) z Dominion operated Millstone Units 2 & 3 in a manner that preserved public health and safety z All cornerstone objectives were met z NRC plans baseline inspections at Millstone for the remainder of the assessment period |
| | |
| | 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 Select What We Do for Public Affairs z Paul Krohn, Branch Chief pgk1@nrc.gov |
| | |
| | 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) |
| | |
| | NEAC Response and Remarks Millstone Nuclear Power Station Unit 2 and Unit 3 |
| | |
| | END OF THE PRESENTATION Nuclear Regulatory Commission - Region I King of Prussia, Pennsylvania March 29, 2006 |
| | |
| | Potential Public Interest Issues Safety Concerns Brought to the NRC z NRC has a formal process z Concerns are reviewed on an individual basis by NRC technical, legal, investigative staff and management z Issues of immediate concern receive prompt attention by NRC and by nuclear power plant management z NRCs process requires reviews of all valid safety issues to ensure they are adequately addressed z NRC implements measures to protect the identity of allegers including not commenting on the existence of a specific allegation |
| | |
| | Potential Public Interest Issues Recent Press Articles on Security Issues z Current NRC policy is to not discuss security matters in a public forum z NRC will not comment on existence of allegations in this area z Notwithstanding these policies, we want to assure the public that if safety issues did exist, the NRC would take prompt action to address them |
| | |
| | Potential Public Interest Issues Strontium-90 (SR-90) z Fission process byproduct (29 year half-life) z Potential sources in the Environment |
| | - 16,800,000 curies - nuclear weapons testing (UNSCEAR 2001) |
| | - 212,000 curies - 1986 Chernobyl accident (UNSCEAR 2001) |
| | - 0.00012 to 0.001 curies - from all 103 operating nuclear power plants z For nuclear reactor releases, SR-89 (50 day half-life) is always present with SR-90 |
| | |
| | Potential Public Interest Issues Strontium-90 (SR-90) continued z Mid 1990s - Release levels of SR-90 were so low that nuclear utilities had difficulty measuring the amounts released z NRC allowed SR-90 monitoring by using goat milk samples z Goat milk samples indicated low levels of SR-90 without the presence of SR-89 (indicating not originating from a nuclear power plant) z Most likely source is from 1950s and 1960s atmospheric nuclear weapons testing |
| | |
| | Potential Public Interest Issues Radiation Exposure to the Public from Background Sources and from Millstone Power Station z Natural |
|
| |
|
| ==Background:== | | ==Background:== |
| Radon Radon --200 200 mremmremCosmic Cosmic --27 27 mremmremCosmogenicCosmogenic | | z Millstone Station Whole Body Dose 2 z Radon - 200 mrem (Maximum) Offsite Individual: |
| --1 1 mremmremTerrestrial Terrestrial | | z Cosmic - 27 mrem z Cosmogenic - 1 mrem z Airborne Effluents - 0.0261 mrem z Terrestrial - 28 mrem z Liquid Effluents - 0.0017 mrem z Internal - 39 mrem z Onsite RadWaste Storage - 0.1400 mrem z Occupational - 0.9 mrem z Nuclear Fuel Cycle - 0.05 mrem z Consumer Products - 5 to 13 mrem |
| --28 28 mremmremInternal Internal --39 39 mremmremOccupational Occupational | | * Approximate Total: 0.17 mrem z Environment - 0.06 mrem z Medical: |
| --0.9 0.9 mremmremNuclear Fuel Cycle Nuclear Fuel Cycle
| | z Diagnostic X- X-rays - 39 mrem z Nuclear Medicine - 14 mrem |
| --0.05 0.05 mremmremConsumer Products Consumer Products
| | * Approximate Total 1: 360 mrem |
| --5 to 13 5 to 13 mremmremEnvironment Environment
| | [ 1 USNRC Site Access Training Manual, October 1999 ] |
| --0.06 0.06 mremmrem Medical: Medical:Diagnostic XDiagnostic X
| | [ 2 Millstone Power Station, 2004 Radioactive Effluents Release Report, Vol. 1 ]}} |
| --rays rays --39 39 mremmremNuclear Medicine Nuclear Medicine | |
| --14 14 mremmrem* Approximate Total
| |
| * Approximate Total 1 1: 360 : 360 mremmremRadiation Exposure to the Public from Background SourcesRadiation Exposure to the Public from Background Sourcesand from Millstone Power Stationand from Millstone Power StationMillstone Station Whole Body Dose Millstone Station Whole Body Dose 2 2(Maximum) Offsite Individual:(Maximum) Offsite Individual:Airborne Effluents Airborne Effluents | |
| --0.0261 0.0261 mremmremLiquid Effluents Liquid Effluents
| |
| --0.0017 0.0017 mremmremOnsite Onsite RadWasteRadWasteStorage Storage --0.1400 0.1400 mremmrem* Approximate Total: 0.17
| |
| * Approximate Total: 0.17 mremmrem[ 1USNRC Site Access Training Manual, October 1999 ]
| |
| [ 2Millstone Power Station, 2004 Radioactive Effluents Release Report, Vol. 1 ]}} | |
|
|---|
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2024-05-14
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NRC & NEAC Meeting Concerning Millstone Station Performance Reactor Oversight Program - CY 2005 Nuclear Regulatory Commission - Region I King of Prussia, Pennsylvania March 29, 2006
Purpose of Todays Meeting A public forum for discussion of Millstone Stations annual performance for CY 2005 NRC will address Millstone Stations performance as discussed in the NRC annual assessment letter to Dominion Nuclear Connecticut, Inc.
NEAC will be given the opportunity to respond to the information, request clarifications, and ask additional questions as needed
Agenda z Introduction z Review of Reactor Oversight Process z National Summary of Plant Performance z Discussion of Millstone Station Performance Results z NEAC Response and Remarks z NRC and NEAC Closing Remarks z Break z NRC available for public questions and comments
Region I Organization Samuel J. Collins Regional Administrator Marc L. Dapas Deputy Regional Administrator Brian E. Holian A. Randolph Blough Director Division of Reactor Projects Director Division of Reactor Safety David C. Lew Marsha K. Gamberoni Deputy Director Deputy Director Paul G. Krohn Regional Specialists Branch Chief Millstone Senior Project Engineers Resident Inspectors Scott Barber Max Schneider Barry Norris Jamie Benjamin Silas Kennedy
NRC Representatives z David C. Lew, Deputy Division Director, DRP
- (610) 337-5229 z Max Schneider, Senior Resident Inspector z Jamie Benjamin, Resident Inspector z Silas Kennedy, Resident Inspector
- (860) 447-3170 z Paul Krohn, Branch Chief
- (610) 337-5120 z Scott Barber, Senior Project Engineer
- (610) 337-5232
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 NRC strategic objective
Reactor Oversight Process 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 ~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
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
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 2005 Licensee Response 84 Regulatory Response 12 Degraded Cornerstone 4 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total 103
National Summary z Performance Indicator Results (at end of CY 2005)
Green 1850 White 4 Yellow 0 Red 0 z Total Inspection Findings (CY 2005)
Green 849 White 10 Yellow 1 Red 0
Millstone Assessment Results (Jan. 1 - Dec. 31, 2005) z Licensee Response Column z No safety significant findings or PIs
Millstone Inspection Activities (Jan. 1 - Dec. 31, 2005)
Hours of inspection related activities
- 5021 hours0.0581 days <br />1.395 hours <br />0.0083 weeks <br />0.00191 months <br /> at Millstone Unit 2
- 6115 hours0.0708 days <br />1.699 hours <br />0.0101 weeks <br />0.00233 months <br /> at Millstone Unit 3 Three resident inspectors assigned to the site
- Jamie Benjamin started at Millstone in June 2005 Inspections Regional Team Units 2 & 3 5 1 Unit 2 only 7 0 Unit 3 only 2 2
Millstone Inspection Activities (Jan. 1 - Dec. 31, 2005)
Inspection findings
- 3 findings of very low safety significance (Green) at Unit 2
- 12 findings of very low safety significance (Green) at Unit 3
- 2 findings of very low safety significance (Green) common to both units Unit 3 refueling outage (09/29 - 10/27/05)
- no findings related to the outage
Millstone Inspection Activities (Jan. 1 - Dec. 31, 2005)
Unit 2 Triennial Fire Protection team inspection
- no findings Unit 2 reactor head replacement inspection
- no findings Unit 3 safety system design team inspection
- no findings Unit 3 Special Inspection Team
- 6 findings of very low safety significance (Green)
Millstone Annual Assessment Summary (Jan. 1 - Dec. 31, 2005) z Dominion operated Millstone Units 2 & 3 in a manner that preserved public health and safety z All cornerstone objectives were met z NRC plans baseline inspections at Millstone for the remainder of the assessment period
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 Select What We Do for Public Affairs z Paul Krohn, Branch Chief pgk1@nrc.gov
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)
NEAC Response and Remarks Millstone Nuclear Power Station Unit 2 and Unit 3
END OF THE PRESENTATION Nuclear Regulatory Commission - Region I King of Prussia, Pennsylvania March 29, 2006
Potential Public Interest Issues Safety Concerns Brought to the NRC z NRC has a formal process z Concerns are reviewed on an individual basis by NRC technical, legal, investigative staff and management z Issues of immediate concern receive prompt attention by NRC and by nuclear power plant management z NRCs process requires reviews of all valid safety issues to ensure they are adequately addressed z NRC implements measures to protect the identity of allegers including not commenting on the existence of a specific allegation
Potential Public Interest Issues Recent Press Articles on Security Issues z Current NRC policy is to not discuss security matters in a public forum z NRC will not comment on existence of allegations in this area z Notwithstanding these policies, we want to assure the public that if safety issues did exist, the NRC would take prompt action to address them
Potential Public Interest Issues Strontium-90 (SR-90) z Fission process byproduct (29 year half-life) z Potential sources in the Environment
- 16,800,000 curies - nuclear weapons testing (UNSCEAR 2001)
- 212,000 curies - 1986 Chernobyl accident (UNSCEAR 2001)
- 0.00012 to 0.001 curies - from all 103 operating nuclear power plants z For nuclear reactor releases, SR-89 (50 day half-life) is always present with SR-90
Potential Public Interest Issues Strontium-90 (SR-90) continued z Mid 1990s - Release levels of SR-90 were so low that nuclear utilities had difficulty measuring the amounts released z NRC allowed SR-90 monitoring by using goat milk samples z Goat milk samples indicated low levels of SR-90 without the presence of SR-89 (indicating not originating from a nuclear power plant) z Most likely source is from 1950s and 1960s atmospheric nuclear weapons testing
Potential Public Interest Issues Radiation Exposure to the Public from Background Sources and from Millstone Power Station z Natural
Background:
z Millstone Station Whole Body Dose 2 z Radon - 200 mrem (Maximum) Offsite Individual:
z Cosmic - 27 mrem z Cosmogenic - 1 mrem z Airborne Effluents - 0.0261 mrem z Terrestrial - 28 mrem z Liquid Effluents - 0.0017 mrem z Internal - 39 mrem z Onsite RadWaste Storage - 0.1400 mrem z Occupational - 0.9 mrem z Nuclear Fuel Cycle - 0.05 mrem z Consumer Products - 5 to 13 mrem
- Approximate Total: 0.17 mrem z Environment - 0.06 mrem z Medical:
z Diagnostic X- X-rays - 39 mrem z Nuclear Medicine - 14 mrem
- Approximate Total 1: 360 mrem
[ 1 USNRC Site Access Training Manual, October 1999 ]
[ 2 Millstone Power Station, 2004 Radioactive Effluents Release Report, Vol. 1 ]
