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{{#Wiki_filter:Braidwood | {{#Wiki_filter:Braidwood Station Annual Assessment Meeting 2009 Reactor Oversight Program Nuclear Regulatory Commission - Region III Braidwood, Illinois June 3, 2010 1 | ||
assessment letter | Purpose of Todays Meeting | ||
*Licensee will be given the opportunity to respond and inform the NRC of new | * A public forum for discussion of the licensees performance in 2009 | ||
* NRC will address the performance issues identified in the annual assessment letter | |||
* Licensee will be given the opportunity to respond and inform the NRC of new or existing programs to maintain or improve performance 2 | |||
Agenda | |||
* Introduction | |||
* Review of Reactor Oversight Process | |||
* National Summary of Plant Performance | |||
* Di Discussion i off Pl Plant Performance P f Results R l | |||
* Licensee Response and Remarks | |||
* NRC Closing Remarks | |||
* Break | |||
* NRC available to address public questions 3 | |||
Who We Are The Atomic Energy Commission was established by Congress in 1946 to encourage the use of nuclear power and regulate its safety In 1974 Congress divided the AEC into two parts U.S. Nuclear Regulatory Commission Department of Energy The NRC is headed by a Chairman and four Commissioners, all appointed i d by b the h President P id and d confirmed fi d byb theh Senate S for f | |||
staggered five-year terms. | |||
Chairman Commissioner Commissioner Commissioner Commissioner Gregory B. Kristine L. George William D. William C. | |||
Jaczko Svinicki Apostolakis Magwood, IV Ostendorff 4 | |||
Region III Organization Mark Satorius Regional Administrator Cindy Pederson Deputy Regional Administrator Division of Reactor Projects Division of Reactor Safety Steven West Anne Boland Director Director Gary Shear Kenneth OBrien Deputy Director Deputy Director Richard Skokowski Regional Specialists Branch Chief Braidwood Region III Staff Resident Inspectors Raymond Ng Jamie Benjamin Meghan-Thorpe Kavanaugh Alex Garmoe 5 | |||
Jaczko Region III | |||
*To license and regulate the | 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. | |||
6 | |||
Some Nuclear Facts | Some Nuclear Facts | ||
*104 nuclear power plants supply about 20 percent of the electricity in the U.S. | * 104 nuclear power plants supply about 20 percent of the electricity in the U.S. | ||
*Nuclear materials are used | * Nuclear materials are used in medicine for diagnosis and cancer treatment. | ||
*Nuclear materials are widely used in industry, such as in density gauges, flow measurement devices, radiography devices, and | * Nuclear materials are widely used in industry, such as in density gauges, flow measurement devices, radiography devices, and irradiators. | ||
7 | |||
The NRC Regulates | The NRC Regulates | ||
*Nuclear reactors | * Nuclear reactors | ||
-commercial power reactors, research and test reactors, new reactor designs | - commercial power reactors, research and test reactors, new reactor designs | ||
*Nuclear materials | * Nuclear materials | ||
- | - nuclear reactor fuel fuel, radioactive materials for medical medical, industrial, and academic use | ||
*Nuclear waste | * Nuclear waste | ||
-transportation, storage and disposal of nuclear material and waste, decommissioning of nuclear facilities | - transportation, storage and disposal of nuclear material and waste, decommissioning of nuclear facilities | ||
*Nuclear security | * Nuclear security | ||
-physical security of nuclear facilities and materials from sabotage or attacks What We | - physical security of nuclear facilities and materials from sabotage or attacks 8 | ||
What We Dont Do | |||
* We do not regulate nuclear weapons, military reactors, or space vehicle reactors | |||
* We do not own or operate nuclear power plants | |||
* We do not regulate some radioactive materials, such as X-rays and naturally occurring radon 9 | |||
How We Regulate | |||
* Establish rules and regulations | |||
* Issue licenses | |||
* Provide oversight through inspection, enforcement, f t andd evaluation l ti off operational experience | |||
* Conduct research to provide support for regulatory decisions | |||
* Respond to events and emergencies 10 | |||
Assurance of Plant Safety | |||
* Require defense-in-depth | |||
* Require long-term maintenance of equipment | |||
* Require continual training of operators | |||
* Verify compliance with regulations 11 | |||
What We Do - Nuclear Waste | |||
* The NRC regulates: | |||
- Storage of spent reactor fuel in fuel pools or dry storage casks and casks, | |||
- Any national spent fuel storage site, such as the proposed Yucca Mountain site. | |||
12 | |||
What We Do - Nuclear Security | |||
* 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. | |||
13 | |||
NRC Performance 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. | |||
14 | |||
Reactor Oversight Process 3 Strategic g Performance Areas are divided into 7 Cornerstones of Safety Inspection Findings and Performance Indicators are assigned to a Cornerstone Inspection Findings can be assigned a cross-cutting aspect (a causal factor for the performance deficiency) | |||
Human Performance Problem Identification and Resolution Safety Conscious Work Environment Numerous findings with a common cross-cutting aspect results in a Substantive Cross-Cutting Issue 15 | |||
Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Inspection Performance Indicator Results Results Significance Significance Evaluation Evaluation Action Matrix Regulatory | |||
===Response=== | |||
16 | |||
Examples of Baseline Inspections Some of the Routine Inspections Conducted at Every Plant | |||
* Equipment Alignment ~80 hrs/yr | |||
* Operator Response ~125 hrs/yr | |||
* Emergency Preparedness ~80 hrs/yr | |||
* Worker Radiation Protection ~95 hrs/yr | |||
* Corrective Action Case Reviews ~60 hrs/yr | |||
* Corrective Action Program ~250 hrs every 2 yrs | |||
* Rad Release Controls ~110 hrs every 2 yrs | |||
* Triennial Fire Protection ~250 hrs every 3 yrs 17 | |||
Significance Threshold Performance Indicators Green: Baseline Inspection Program White: Increased NRC oversight Yellow: | |||
Yellow Increased NRC oversight Red: Increased NRC oversight Inspection Findings Green: Very low safety significance White: Low to moderate safety significance Yellow: | |||
Yellow Substantial safety significance Red: High safety significance 18 | |||
Action Matrix Concept Multiple/Rep. | |||
Licensee Regulatory Degraded Unacceptable Degraded Response Response Cornerstone Performance Cornerstone Increased safety significance of findings and performance indicators results in movement to the right Movement to the right results in: | |||
NRC supplemental inspections Increased Management Involvement Increased Regulatory Actions 19 | |||
National Summary of Plant Performance as of 12/31/2009 Licensee Response 79 Regulatory Response 24 Degraded Cornerstone 1 Multiple/Repetitive Degraded Cornerstone 0 Unacceptable 0 Total 104 20 | |||
2009 National Summary | |||
* Performance Indicator Results Green 7039 White 18 Yellow 0 Red 0 | |||
* Total Inspection Findings Green 879 White 7 Yellow 0 Red 0 21 | |||
Braidwood Assessment Results January 1 - December 31, 2009 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Licensee Licensee Licensee Regulatory Unit 1 Response Response Response Response Licensee Licensee Licensee Licensee Unit 2 Response Response Response Response | |||
* | * One White Finding identified associated with a Unit 1 emergency core cooling valve failing to stroke open during periodic testing | ||
* 16 Green findings and 1 Severity Level IV violation | |||
* All performance indicators were Green | |||
* Human Performance Substantive Cross-Cutting Issue remains open 22 | |||
Braidwood Assessment Results January 1 - December 31, 2009 | |||
* Human Performance Substantive Cross-Cutting Issue regarding conservative assumptions in decision-making remains open | |||
*Issue | - IInitially iti ll opened d in i July J l 2009 | ||
- Licensee has implemented comprehensive improvement actions | |||
- NRC will continue to evaluate the effectiveness of the licensees actions 23 | |||
for | Safety Significant Findings or PIs January 1 - December 31, 2009 | ||
* One White Finding identified for Unit 1 | |||
- Emergency core cooling system valve failed a periodic surveillance test | |||
- Purpose of the valve is to provide a secondary source of cooling water to the emergency core cooling system after the useable volume of primary water runs out | |||
- Cause of the valve failure was corrosion of the valve torque switch due to standing water in the valve actuator housing | |||
- Source of the water was rainwater leaking through a roof hatch and dripping into an open-ended conduit containing a cable associated with the valve 24 | |||
Braidwood Inspection Activities January 1 - December 31, 2009 Examples of inspections conducted in addition to daily resident inspector activities | |||
* | * Dry Cask Storage Infrastructure Construction (Ongoing) | ||
* Triennial Fire Protection Inspection (January 26 to March 6) | |||
* Unit 1 Refueling Outage (March 30 to April 19 | |||
* Initial Operator License Examination (October 5 to 29) | |||
* Unit 2 Refueling Outage (October 12 to 29) 25 | |||
Braidwood Annual Assessment Summary January 1 - December 31, 2009 | |||
* Exelon operated Braidwood Units 1 & 2 in a manner that preserved public health and safety. | |||
* All cornerstone objectives were met | |||
* One White Finding was identified for Unit 1 | |||
* Human Performance Substantive Cross-Cutting Issue remains open | |||
* NRC will increase oversight of Braidwood Unit 1 in 2010 through a supplemental inspection to evaluate actions taken in response to the White Finding 26 | |||
Licensee Response and Remarks Amir Shahkarami Site Vice President, Braidwood Exelon Nuclear 27 | |||
Open to the Public | |||
- | * The NRC places a high priority on keeping the public and stakeholders informed of its activities. | ||
* At www.nrc.gov you can: | |||
- Review NRC inspection reports | |||
- Find public meeting dates and transcripts | |||
- Read NRC testimony, speeches, press releases, and policy decisions | |||
- Access the agencys Electronic Reading Room to find NRC publications and documents 28 | |||
Contacting the NRC | |||
NRC | * Report an emergency | ||
- (301) 816-5100 (collect calls accepted) | |||
* Report a safety concern | |||
- (800) 695-7403 | |||
* | - Allegation@nrc.gov | ||
* General information or questions | |||
- www.nrc.gov | |||
- Select What We Do for Public Affairs 29 | |||
NRC Representatives | |||
* | * Steven West, Director, Division of Reactor Projects | ||
* | - (630) 829-9600 | ||
* | * Gary Shear, Deputy Division Director, DRP | ||
* | - (630) 829-9601 | ||
* Marshall David, Project Manager, NRR | |||
- ((301)) 415-1547 | |||
* Jamie Benjamin, Senior Resident Inspector | |||
- (815) 458-2852 | |||
* Alex Garmoe, Resident Inspector | |||
- (815) 458-2852 | |||
* Richard Skokowski, Branch Chief, DRP | |||
- (630) 829-9620 | |||
* Raymond Ng, Senior Project Engineer, DRP | |||
- (630) 829-9574 30 | |||
NRC Representatives | |||
* | * Christine Lipa, Chief, Decommissioning Branch (ISFSI) | ||
- | - (630) 829-9834 | ||
* Viktoria Mitlyng, Public Affairs Officer | |||
- | - (630) 829-9662 | ||
* Prema Chandrathil, Public Affairs Officer | |||
* | - (630) 829-9663 | ||
* NRC Region III Office Switchboard | |||
- (630) 829-9500 (800) 522-3025 31 | |||
Reference Sources | |||
* | * Reactor Oversight Process | ||
* | - http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html | ||
* Public Electronic Reading Room | |||
- http://www.nrc.gov/reading-rm.html | |||
* Public Document Room 800-397-4209 (Toll Free) 32 | |||
Braidwood Station Annual Assessment Meeting 2009 Reactor Oversight Program Nuclear Regulatory Commission - Region III Braidwood, Illinois June 3, 2010 33}} | |||
Braidwood |
Latest revision as of 18:24, 13 November 2019
ML101590159 | |
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Site: | Braidwood |
Issue date: | 06/03/2010 |
From: | NRC/RGN-III |
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References | |
Download: ML101590159 (33) | |
Text
Braidwood Station Annual Assessment Meeting 2009 Reactor Oversight Program Nuclear Regulatory Commission - Region III Braidwood, Illinois June 3, 2010 1
Purpose of Todays Meeting
- A public forum for discussion of the licensees performance in 2009
- NRC will address the performance issues identified in the annual assessment letter
- Licensee will be given the opportunity to respond and inform the NRC of new or existing programs to maintain or improve performance 2
Agenda
- Introduction
- Review of Reactor Oversight Process
- National Summary of Plant Performance
- Di Discussion i off Pl Plant Performance P f Results R l
- Licensee Response and Remarks
- NRC Closing Remarks
- Break
- NRC available to address public questions 3
Who We Are The Atomic Energy Commission was established by Congress in 1946 to encourage the use of nuclear power and regulate its safety In 1974 Congress divided the AEC into two parts U.S. Nuclear Regulatory Commission Department of Energy The NRC is headed by a Chairman and four Commissioners, all appointed i d by b the h President P id and d confirmed fi d byb theh Senate S for f
staggered five-year terms.
Chairman Commissioner Commissioner Commissioner Commissioner Gregory B. Kristine L. George William D. William C.
Jaczko Svinicki Apostolakis Magwood, IV Ostendorff 4
Region III Organization Mark Satorius Regional Administrator Cindy Pederson Deputy Regional Administrator Division of Reactor Projects Division of Reactor Safety Steven West Anne Boland Director Director Gary Shear Kenneth OBrien Deputy Director Deputy Director Richard Skokowski Regional Specialists Branch Chief Braidwood Region III Staff Resident Inspectors Raymond Ng Jamie Benjamin Meghan-Thorpe Kavanaugh Alex Garmoe 5
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.
6
Some Nuclear Facts
- 104 nuclear power plants supply about 20 percent of the electricity in the U.S.
- Nuclear materials are used in medicine for diagnosis and cancer treatment.
- Nuclear materials are widely used in industry, such as in density gauges, flow measurement devices, radiography devices, and irradiators.
7
The NRC Regulates
- Nuclear reactors
- commercial power reactors, research and test reactors, new reactor designs
- Nuclear materials
- nuclear reactor fuel fuel, radioactive materials for medical medical, industrial, and academic use
- Nuclear waste
- transportation, storage and disposal of nuclear material and waste, decommissioning of nuclear facilities
- Nuclear security
- physical security of nuclear facilities and materials from sabotage or attacks 8
What We Dont Do
- We do not regulate nuclear weapons, military reactors, or space vehicle reactors
- We do not own or operate nuclear power plants
- We do not regulate some radioactive materials, such as X-rays and naturally occurring radon 9
How We Regulate
- Establish rules and regulations
- Issue licenses
- Provide oversight through inspection, enforcement, f t andd evaluation l ti off operational experience
- Conduct research to provide support for regulatory decisions
- Respond to events and emergencies 10
Assurance of Plant Safety
- Require defense-in-depth
- Require long-term maintenance of equipment
- Require continual training of operators
- Verify compliance with regulations 11
What We Do - Nuclear Waste
- The NRC regulates:
- Storage of spent reactor fuel in fuel pools or dry storage casks and casks,
- Any national spent fuel storage site, such as the proposed Yucca Mountain site.
12
What We Do - Nuclear Security
- 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.
13
NRC Performance 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.
14
Reactor Oversight Process 3 Strategic g Performance Areas are divided into 7 Cornerstones of Safety Inspection Findings and Performance Indicators are assigned to a Cornerstone Inspection Findings can be assigned a cross-cutting aspect (a causal factor for the performance deficiency)
Human Performance Problem Identification and Resolution Safety Conscious Work Environment Numerous findings with a common cross-cutting aspect results in a Substantive Cross-Cutting Issue 15
Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Inspection Performance Indicator Results Results Significance Significance Evaluation Evaluation Action Matrix Regulatory
Response
16
Examples of Baseline Inspections Some of the Routine Inspections Conducted at Every Plant
- Equipment Alignment ~80 hrs/yr
- Operator Response ~125 hrs/yr
- Emergency Preparedness ~80 hrs/yr
- Worker Radiation Protection ~95 hrs/yr
- Corrective Action Case Reviews ~60 hrs/yr
- Corrective Action Program ~250 hrs every 2 yrs
- Rad Release Controls ~110 hrs every 2 yrs
- Triennial Fire Protection ~250 hrs every 3 yrs 17
Significance Threshold Performance Indicators Green: Baseline Inspection Program White: Increased NRC oversight Yellow:
Yellow Increased NRC oversight Red: Increased NRC oversight Inspection Findings Green: Very low safety significance White: Low to moderate safety significance Yellow:
Yellow Substantial safety significance Red: High safety significance 18
Action Matrix Concept Multiple/Rep.
Licensee Regulatory Degraded Unacceptable Degraded Response Response Cornerstone Performance Cornerstone Increased safety significance of findings and performance indicators results in movement to the right Movement to the right results in:
NRC supplemental inspections Increased Management Involvement Increased Regulatory Actions 19
National Summary of Plant Performance as of 12/31/2009 Licensee Response 79 Regulatory Response 24 Degraded Cornerstone 1 Multiple/Repetitive Degraded Cornerstone 0 Unacceptable 0 Total 104 20
2009 National Summary
- Performance Indicator Results Green 7039 White 18 Yellow 0 Red 0
- Total Inspection Findings Green 879 White 7 Yellow 0 Red 0 21
Braidwood Assessment Results January 1 - December 31, 2009 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Licensee Licensee Licensee Regulatory Unit 1 Response Response Response Response Licensee Licensee Licensee Licensee Unit 2 Response Response Response Response
- One White Finding identified associated with a Unit 1 emergency core cooling valve failing to stroke open during periodic testing
- 16 Green findings and 1 Severity Level IV violation
- All performance indicators were Green
- Human Performance Substantive Cross-Cutting Issue remains open 22
Braidwood Assessment Results January 1 - December 31, 2009
- Human Performance Substantive Cross-Cutting Issue regarding conservative assumptions in decision-making remains open
- IInitially iti ll opened d in i July J l 2009
- Licensee has implemented comprehensive improvement actions
- NRC will continue to evaluate the effectiveness of the licensees actions 23
Safety Significant Findings or PIs January 1 - December 31, 2009
- One White Finding identified for Unit 1
- Emergency core cooling system valve failed a periodic surveillance test
- Purpose of the valve is to provide a secondary source of cooling water to the emergency core cooling system after the useable volume of primary water runs out
- Cause of the valve failure was corrosion of the valve torque switch due to standing water in the valve actuator housing
- Source of the water was rainwater leaking through a roof hatch and dripping into an open-ended conduit containing a cable associated with the valve 24
Braidwood Inspection Activities January 1 - December 31, 2009 Examples of inspections conducted in addition to daily resident inspector activities
- Dry Cask Storage Infrastructure Construction (Ongoing)
- Triennial Fire Protection Inspection (January 26 to March 6)
- Unit 1 Refueling Outage (March 30 to April 19
- Initial Operator License Examination (October 5 to 29)
- Unit 2 Refueling Outage (October 12 to 29) 25
Braidwood Annual Assessment Summary January 1 - December 31, 2009
- Exelon operated Braidwood Units 1 & 2 in a manner that preserved public health and safety.
- All cornerstone objectives were met
- One White Finding was identified for Unit 1
- Human Performance Substantive Cross-Cutting Issue remains open
- NRC will increase oversight of Braidwood Unit 1 in 2010 through a supplemental inspection to evaluate actions taken in response to the White Finding 26
Licensee Response and Remarks Amir Shahkarami Site Vice President, Braidwood Exelon Nuclear 27
Open to the Public
- The NRC places a high priority on keeping the public and stakeholders informed of its activities.
- At www.nrc.gov you can:
- Review NRC inspection reports
- Find public meeting dates and transcripts
- Read NRC testimony, speeches, press releases, and policy decisions
- Access the agencys Electronic Reading Room to find NRC publications and documents 28
Contacting the NRC
- Report an emergency
- (301) 816-5100 (collect calls accepted)
- Report a safety concern
- (800) 695-7403
- Allegation@nrc.gov
- General information or questions
- www.nrc.gov
- Select What We Do for Public Affairs 29
NRC Representatives
- Steven West, Director, Division of Reactor Projects
- (630) 829-9600
- Gary Shear, Deputy Division Director, DRP
- (630) 829-9601
- Marshall David, Project Manager, NRR
- ((301)) 415-1547
- Jamie Benjamin, Senior Resident Inspector
- (815) 458-2852
- Alex Garmoe, Resident Inspector
- (815) 458-2852
- Richard Skokowski, Branch Chief, DRP
- (630) 829-9620
- Raymond Ng, Senior Project Engineer, DRP
- (630) 829-9574 30
NRC Representatives
- Christine Lipa, Chief, Decommissioning Branch (ISFSI)
- (630) 829-9834
- Viktoria Mitlyng, Public Affairs Officer
- (630) 829-9662
- Prema Chandrathil, Public Affairs Officer
- (630) 829-9663
- NRC Region III Office Switchboard
- (630) 829-9500 (800) 522-3025 31
Reference Sources
- Reactor Oversight Process
- http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html
- Public Electronic Reading Room
- http://www.nrc.gov/reading-rm.html
- Public Document Room 800-397-4209 (Toll Free) 32
Braidwood Station Annual Assessment Meeting 2009 Reactor Oversight Program Nuclear Regulatory Commission - Region III Braidwood, Illinois June 3, 2010 33