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| issue date = 05/13/2009 | | issue date = 05/13/2009 | ||
| title = Annual Assessment Meeting, Slides for May 28, 2009 Public Meeting | | title = Annual Assessment Meeting, Slides for May 28, 2009 Public Meeting | ||
| author name = Bellamy | | author name = Bellamy R | ||
| author affiliation = NRC/RGN-I/DRP/PB6 | | author affiliation = NRC/RGN-I/DRP/PB6 | ||
| addressee name = | | addressee name = | ||
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=Text= | =Text= | ||
{{#Wiki_filter:Oyster Creek Annual Assessment Meeting 2008 Reactor Oversight Process May 28, | {{#Wiki_filter:Oyster Creek Annual Assessment Meeting 2008 Reactor Oversight Process May 28, 2009 Nuclear Regulatory Commission - Region I | ||
new or existing programs to maintain or | Purpose of Todays Meeting | ||
* Discuss OC performance for 2008 | |||
* Provide Exelon the opportunity to respond to the NRCs annual performance assessment and to identify new or existing programs to maintain or improve performance | |||
* Provide stakeholders the opportunity to engage the NRC staff on plant performance issues and our role in ensuring safe plant operations 2 | |||
Agenda | |||
* | * Introduction | ||
* NRC Organization and Performance Goals | |||
* Reactor Oversight Process (ROP) | |||
* National Summary of Plant Performance | |||
* OC Plant Performance Assessment | |||
* Exelon Response and Remarks | |||
* NRC Closing Remarks | |||
* Break | |||
* NRC available to address public questions 3 | |||
Region I Organization Samuel J. Collins Regional Administrator Marc L. Dapas Deputy Regional Administrator Division of Reactor Safety Division of Reactor Projects Division of Nuclear Materials Safety Darrell J. Roberts, Director David C. Lew, Director John D. Kinneman, Director Peter Wilson, Acting Deputy Director James W. Clifford, Deputy Director Daniel S. Collins, Deputy Director Ronald Bellamy Regional Specialists Regional Specialists Branch 6 Chief OC Resident Inspection Staff Project Engineers Marc Ferdas, Senior Resident Inspector Scott Barber, Senior Project Engineer Jeff Kulp, Resident Inspector Christopher Newport, Project Engineer 4 | |||
NRC Strategic Plan 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 5 | |||
NRC Regulatory Functions What We Regulate | |||
* Nuclear Reactors | |||
* | * Commercial power, research, test, and new reactor designs | ||
* | * Nuclear Material | ||
* | * Reactor fuel, radioactive material for medical, industrial, and academic uses | ||
* | * Nuclear Waste | ||
* | * Transportation, storage, disposal, and facility decommissioning | ||
* | * Nuclear Security | ||
* | * Facility physical security 6 | ||
* | |||
Reactor Oversight Process 3 Strategic Areas & 7 Cornerstones Reactor Radiation Safeguards Safety Safety Public Occupational Initiating Mitigating Barrier Emergency Physical Radiation Radiation Events Systems Integrity Preparedness Protection Safety Safety 7 | |||
Reactor Oversight Process S tra te g ic P e rfo r m a n c e A re a s S a fety C o rn e r s to n e s B a s e lin e In s p e c tio n P e r fo r m a n c e In d ic a to r R e s u lts R e s u lts S ig n ific a n c e S ig n ific a n c e T h r e s h o ld T h r e s h o ld A c tio n M a tr ix R e g u la to ry R e s p o n s e 8 | |||
Examples of Baseline Inspection Areas | |||
* | * Maintenance Effectiveness | ||
* | * Operability Evaluations | ||
* | * Post-Maintenance Testing | ||
* | * Refueling & Outage Activities | ||
* | * Surveillance Testing | ||
* Emergency Preparedness Assessment | |||
* Occupational Radiation Safety | |||
* Public Radiation Safety | |||
* Performance Indicator Verification | |||
* Fire Protection | |||
* Identification & Resolution of Problems | |||
* Follow-up of Events 9 | |||
of the NRC | NRC Performance Indicators | ||
*NRC plans baseline inspections at OC for | * Initiating Events PIs | ||
* Mitigating Systems PIs | |||
* Barrier Integrity PIs | |||
* Emergency Planning PIs | |||
* Radiation Protection PIs | |||
* Security PIs are not Publicly Available 10 | |||
Significance Threshold Performance Indicators Green Baseline Inspection White Requires additional NRC oversight Yellow Requires more NRC oversight Red Requires most NRC oversight Inspection Findings Green Very low safety issue White Low to moderate safety issue Yellow Substantial safety issue Red High safety issue 11 | |||
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 12 | |||
National Summary of Plant Performance (at end of 2008) | |||
Licensee Response 86 Regulatory Response 14 Degraded Cornerstone 3 Multiple/Repetitive Degraded Cornerstone 1 Unacceptable 0 Total 104 13 | |||
National Summary of Plant Performance (at end of 2008) | |||
Performance Indicator Results Green 1762 White 6 Yellow 0 Red 0 Total Inspection Findings Green 776 White 17 Yellow 0 Red 0 14 | |||
NRC Inspection Activities at OC (for 2008) | |||
* 6158 hours of inspection and related activities | |||
* 2 resident inspectors on-site | |||
* 13 regional inspections | |||
* 3 major team inspections: | |||
Problem Identification & Resolution Triennial Fire Protection License Renewal Commitments 15 | |||
OC PIs / Findings (January 1 - December 31, 2008) | |||
* All Green Performance Indicators | |||
* Nine (9) Green / Severity Level - IV inspection findings 16 | |||
NRC Inspection Findings at OC | |||
* Diesel Driven Fire Pump Unavailable Due to Improper Testing | |||
* Improper Valve Reassembly Results in Instrument Air Transient | |||
* Core Alterations Performed Without Required Source Range Nuclear Instrument Monitor Configuration | |||
* Inadequate Risk Assessment Identified Prior to Commencement of Maintenance on Bank 6 Startup Transformer | |||
* Potential Preconditioning of Core Spray Valves Prior to ASME In-service Test | |||
* Conduct of Maintenance Procedure Not Properly Implemented for 480 volt Breaker Maintenance | |||
* Scaffold Installation Procedure not Properly Implemented | |||
* Instrument Air Transient due to Insufficient Preventive Maintenance on Service Air Compressors | |||
* Failure to Review the Impact of Site Staffing Changes to the Fire Protection Program 17 | |||
NRC Annual Assessment Summary for OC | |||
* Exelon operated the plant safely and in a manner that preserved public health and safety and protected the environment | |||
* OC was in the Licensee Response column of the NRCs Action Matrix for the last quarter of 2008 | |||
* NRC plans baseline inspections at OC for the remainder of 2009 18 | |||
Licensee Response and Remarks Mr. T. Rausch Site Vice President - Oyster Creek Exelon Generation Company, LLC 19 | |||
Contacting the NRC | |||
* Report a safety concern: | |||
(800) 695-7403 Allegation@nrc.gov | |||
* General information or questions: | |||
www.nrc.gov Public Affairs Officers: | |||
Diane Screnci 610-337-5330 Neil Sheehan 610-337-5331 20 | |||
NRC Representatives | |||
* David C. Lew, Division Director, DRP 610-337-5229 | |||
* James W. Clifford, Deputy Division Director, DRP 610-337-5080 | |||
* Ronald Bellamy, Branch Chief 610-337-5200 | |||
* Marc Ferdas, Senior Resident Inspector 609-693-0702 | |||
* Jeff Kulp, Resident Inspector 609-693-0702 | |||
* Scott Barber, Senior Project Engineer 610-337-5232 21 | |||
Reference Sources | |||
* Reactor Oversight Process | |||
* http://www.nrc.gov/NRR/OVERSIGHT/ASS ESS/index.html | |||
* Public Electronic Reading Room http://www.nrc.gov/reading-rm.html | |||
* Public Document Room 1-800-397-4209 (Toll Free) 22 | |||
End of the Presentation Nuclear Regulatory Commission Region I King of Prussia, Pennsylvania May 28, 2009}} | End of the Presentation Nuclear Regulatory Commission Region I King of Prussia, Pennsylvania May 28, 2009}} |
Latest revision as of 06:57, 14 November 2019
ML091320652 | |
Person / Time | |
---|---|
Site: | Oyster Creek |
Issue date: | 05/13/2009 |
From: | Bellamy R NRC/RGN-I/DRP/PB6 |
To: | |
BELLAMY RR | |
References | |
MN 09-020 | |
Download: ML091320652 (23) | |
Text
Oyster Creek Annual Assessment Meeting 2008 Reactor Oversight Process May 28, 2009 Nuclear Regulatory Commission - Region I
Purpose of Todays Meeting
- Discuss OC performance for 2008
- Provide Exelon the opportunity to respond to the NRCs annual performance assessment and to identify new or existing programs to maintain or improve performance
- Provide stakeholders the opportunity to engage the NRC staff on plant performance issues and our role in ensuring safe plant operations 2
Agenda
- Introduction
- NRC Organization and Performance Goals
- Reactor Oversight Process (ROP)
- National Summary of Plant Performance
- OC Plant Performance Assessment
- Exelon Response and Remarks
- NRC Closing Remarks
- Break
- NRC available to address public questions 3
Region I Organization Samuel J. Collins Regional Administrator Marc L. Dapas Deputy Regional Administrator Division of Reactor Safety Division of Reactor Projects Division of Nuclear Materials Safety Darrell J. Roberts, Director David C. Lew, Director John D. Kinneman, Director Peter Wilson, Acting Deputy Director James W. Clifford, Deputy Director Daniel S. Collins, Deputy Director Ronald Bellamy Regional Specialists Regional Specialists Branch 6 Chief OC Resident Inspection Staff Project Engineers Marc Ferdas, Senior Resident Inspector Scott Barber, Senior Project Engineer Jeff Kulp, Resident Inspector Christopher Newport, Project Engineer 4
NRC Strategic Plan 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 5
NRC Regulatory Functions What We Regulate
- Nuclear Reactors
- Commercial power, research, test, and new reactor designs
- Nuclear Material
- Reactor fuel, radioactive material for medical, industrial, and academic uses
- Nuclear Waste
- Transportation, storage, disposal, and facility decommissioning
- Nuclear Security
- Facility physical security 6
Reactor Oversight Process 3 Strategic Areas & 7 Cornerstones Reactor Radiation Safeguards Safety Safety Public Occupational Initiating Mitigating Barrier Emergency Physical Radiation Radiation Events Systems Integrity Preparedness Protection Safety Safety 7
Reactor Oversight Process S tra te g ic P e rfo r m a n c e A re a s S a fety C o rn e r s to n e s B a s e lin e In s p e c tio n P e r fo r m a n c e In d ic a to r R e s u lts R e s u lts S ig n ific a n c e S ig n ific a n c e T h r e s h o ld T h r e s h o ld A c tio n M a tr ix R e g u la to ry R e s p o n s e 8
Examples of Baseline Inspection Areas
- Maintenance Effectiveness
- Operability Evaluations
- Post-Maintenance Testing
- Refueling & Outage Activities
- Surveillance Testing
- Emergency Preparedness Assessment
- Performance Indicator Verification
- Fire Protection
- Identification & Resolution of Problems
- Follow-up of Events 9
NRC Performance Indicators
- Emergency Planning PIs
- Radiation Protection PIs
- Security PIs are not Publicly Available 10
Significance Threshold Performance Indicators Green Baseline Inspection White Requires additional NRC oversight Yellow Requires more NRC oversight Red Requires most NRC oversight Inspection Findings Green Very low safety issue White Low to moderate safety issue Yellow Substantial safety issue Red High safety issue 11
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 12
National Summary of Plant Performance (at end of 2008)
Licensee Response 86 Regulatory Response 14 Degraded Cornerstone 3 Multiple/Repetitive Degraded Cornerstone 1 Unacceptable 0 Total 104 13
National Summary of Plant Performance (at end of 2008)
Performance Indicator Results Green 1762 White 6 Yellow 0 Red 0 Total Inspection Findings Green 776 White 17 Yellow 0 Red 0 14
NRC Inspection Activities at OC (for 2008)
- 6158 hours0.0713 days <br />1.711 hours <br />0.0102 weeks <br />0.00234 months <br /> of inspection and related activities
- 2 resident inspectors on-site
- 13 regional inspections
- 3 major team inspections:
Problem Identification & Resolution Triennial Fire Protection License Renewal Commitments 15
OC PIs / Findings (January 1 - December 31, 2008)
- All Green Performance Indicators
- Nine (9) Green / Severity Level - IV inspection findings 16
NRC Inspection Findings at OC
- Diesel Driven Fire Pump Unavailable Due to Improper Testing
- Improper Valve Reassembly Results in Instrument Air Transient
- Core Alterations Performed Without Required Source Range Nuclear Instrument Monitor Configuration
- Inadequate Risk Assessment Identified Prior to Commencement of Maintenance on Bank 6 Startup Transformer
- Potential Preconditioning of Core Spray Valves Prior to ASME In-service Test
- Conduct of Maintenance Procedure Not Properly Implemented for 480 volt Breaker Maintenance
- Scaffold Installation Procedure not Properly Implemented
- Instrument Air Transient due to Insufficient Preventive Maintenance on Service Air Compressors
- Failure to Review the Impact of Site Staffing Changes to the Fire Protection Program 17
NRC Annual Assessment Summary for OC
- Exelon operated the plant safely and in a manner that preserved public health and safety and protected the environment
- OC was in the Licensee Response column of the NRCs Action Matrix for the last quarter of 2008
- NRC plans baseline inspections at OC for the remainder of 2009 18
Licensee Response and Remarks Mr. T. Rausch Site Vice President - Oyster Creek Exelon Generation Company, LLC 19
Contacting the NRC
- Report a safety concern:
(800) 695-7403 Allegation@nrc.gov
- General information or questions:
www.nrc.gov Public Affairs Officers:
Diane Screnci 610-337-5330 Neil Sheehan 610-337-5331 20
NRC Representatives
- David C. Lew, Division Director, DRP 610-337-5229
- James W. Clifford, Deputy Division Director, DRP 610-337-5080
- Ronald Bellamy, Branch Chief 610-337-5200
- Marc Ferdas, Senior Resident Inspector 609-693-0702
- Jeff Kulp, Resident Inspector 609-693-0702
- Scott Barber, Senior Project Engineer 610-337-5232 21
Reference Sources
- Reactor Oversight Process
- http://www.nrc.gov/NRR/OVERSIGHT/ASS ESS/index.html
- Public Electronic Reading Room http://www.nrc.gov/reading-rm.html
- Public Document Room 1-800-397-4209 (Toll Free) 22
End of the Presentation Nuclear Regulatory Commission Region I King of Prussia, Pennsylvania May 28, 2009