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{{#Wiki_filter:NRC Annual Performance Assessment of Seabrook 2007 Reactor Oversight Program | {{#Wiki_filter:NRC Annual Performance Assessment of Seabrook 2007 Reactor Oversight Program | ||
Performance Assessment and discuss new or existing programs to improve performance Provide the public an opportunity to discuss plant performance and the | Purpose of Todays Meeting | ||
* Discuss Seabrook Plant Performance for CY 2007 | |||
* Provide FPL Energy the opportunity to respond to the NRCs Annual Performance Assessment and discuss new or existing programs to improve performance | |||
* Provide the public an opportunity to discuss plant performance and the NRCs role in ensuring safe plant operations with the NRC staff 2 | |||
Agenda | |||
* Introduction | |||
* NRC Organization and Performance Goals | |||
* Reactor Oversight Process (ROP) | |||
* National Summary of Plant Performance | |||
* Seabrooks Plant Performance Assessment | |||
* FPL Energys Response and Remarks | |||
* NRC Closing Remarks | |||
* Break | |||
* NRC available to address public questions 3 | |||
Region I Organization Samuel J. Collins Regional Administrator Marc J. Dapas Deputy Regional Administrator David C. Lew Marsha K. Gamberoni Director Division of Reactor Projects Director Division of Reactor Safety James W. Clifford Darrell J. Roberts Deputy Director Deputy Director Arthur L. Burritt Regional Specialists Branch Chief Seabrook Resident Inspectors William Raymond - Senior RI Project Engineers Peter Presby - RI (acting) Leonard Cline - Senior PE Joyce C. Tomlinson - PE 4 | |||
- | |||
- | |||
NRC Representatives | |||
* Arthur L. Burritt, Branch Chief (610) 337-5069 | |||
* William Raymond, SRI (603) 474-3589 | |||
* Peter Presby, RI (acting) | |||
(603) 474-3589 | |||
* Ross Moore, (in training) 5 | |||
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 6 | |||
2007 | 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 | ||
End of the | 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 | ||
Typical Baseline Inspection Areas | |||
* Equipment Alignment | |||
* Fire Protection | |||
* Operator Response | |||
* Emergency Preparedness | |||
* Radiation Release Controls | |||
* Worker Radiation Protection | |||
* Corrective Action Program 9 | |||
Significance Threshold Performance Indicators | |||
Green Baseline Inspection | |||
White May increase NRC oversight | |||
Yellow Requires more NRC oversight | |||
Red Requires the most NRC oversight Inspection Findings | |||
Green Very low safety issue | |||
White Low to moderate safety issue | |||
Yellow Substantial safety issue | |||
Red High safety issue 10 | |||
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 11 | |||
National Summary (at end of 2007) | |||
Licensee Response 87 Regulatory Response 8 Degraded Cornerstone 8 Multiple/Repetitive Degraded Cornerstone 1 Unacceptable 0 Total 104 12 | |||
National Summary (at end of 2007) | |||
Performance Indicator Results | |||
Green 1954 | |||
White 8 | |||
Yellow 2 | |||
Red 0 Total Inspection Findings | |||
Green 918 | |||
White 9 | |||
Yellow 2 | |||
Red 0 13 | |||
NRC 2007 Annual Assessment for Seabrook | |||
* FPL Energy operated Seabrook in a manner that preserved public health and safety and protected the environment | |||
* All cornerstone objectives were fully met | |||
* Seabrook was in the Licensee Response column of the NRCs Action Matrix for all four quarters of 2007 | |||
* NRC plans baseline inspections at Seabrook for the remainder of CY 2008 14 | |||
NRC Inspection Activities at Seabrook | |||
* 6000+ hours of inspection related activities | |||
* 2329 hours of direct inspection activities | |||
* 2 resident inspectors on-site | |||
* 13 Regional Specialist inspections 15 | |||
NRC Inspection Activities | |||
* Team Inspections | |||
- Component Design Basis team inspection | |||
* Supplemental inspections | |||
- Emergency Diesel Generators 16 | |||
Safety Significant PIs / Findings | |||
* All Performance Indicators in the Reactor and Radiation Safety Areas at Seabrook remained GREEN throughout 2007 | |||
* Inspectors documented six GREEN inspection findings in the Reactor and Radiation Safety Areas at Seabrook in 2007 17 | |||
NRC Inspection Findings | |||
* Green - Enclosure building air handling fan power supply cable connections not torqued per procedures. | |||
* Green - Inadequate testing of the alternate cooling water supply resulted in failure of alternate cooling water to centrifugal charging pump lube oil coolers | |||
* Green - Inadequate corrective actions resulted in multiple voltage regulator failures of the B EDG 18 | |||
NRC 2007 Assessment Summary for Seabrook | |||
* FPL Energy operated Seabrook in a manner that preserved public health and safety and protected the environment. | |||
* Seabrook was in the Licensee Response Column of the Action Matrix for all of 2007. | |||
* NRC plans baseline inspections for the remainder of 2008. | |||
19 | |||
Licensee Response and Remarks Mr. G. St. Pierre Site Vice President - Seabrook FPL Energy 20 | |||
Contacting the NRC | |||
* Report an emergency: | |||
(301) 816-5100 (call collect) | |||
* Report a safety concern: | |||
(800) 695-7403 | |||
Allegation@nrc.gov | |||
* General information or questions: | |||
www.nrc.gov | |||
Select Public Meetings & Involvement or Contact Us 21 | |||
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 1-800-397-4209 (Toll Free) 22 | |||
End of the Presentation Nuclear Regulatory Commission - Region I King of Prussia, Pennsylvania March 25, 2008 | |||
NRC Performance Indicators Initiating Events PIs | |||
* Unplanned Scrams | |||
* Unplanned Scrams with Complications | |||
* Unplanned Power Changes Mitigating Systems PIs | |||
* Emergency AC Power System | |||
* High Pressure Injection System | |||
* Residual Heat Removal System | |||
* Cooling Water Support Systems | |||
* Safety System Functional Failures Barrier Integrity PIs | |||
* Reactor Coolant System Specific Activity | |||
* Reactor Coolant System Leakage Emergency Planning PIs | |||
* Drill / Exercise Performance | |||
* Emergency Response Organization Participation | |||
* Alert and Notification System Radiation Protection PIs | |||
* Occupational Exposure Control Effectiveness | |||
* RETS / ODCM Radiological Effluent Security PIs are not Publicly Available 24 | |||
Seabrook Performance Indicators Occupational RETS/ODCM Unplanned Emergency AC RCS Specific Drill/Exercise Security Exposure Control Radiological Scrams (G) Power System (G) Activity (G) Performance (G) (Not Public) | |||
Effectiveness (G) Effluent (G) | |||
Unplanned High Pressure ERO Drill Scrams with Injection System RCS Leakage (G) | |||
Participation (G) | |||
Complications (G) (G) | |||
Residual Heat Alert and Unplanned Power Removal System Notification Changes (G) | |||
(G) System (G) | |||
Heat Removal System (G) | |||
Cooling Water Systems (G) | |||
Safety System Functional Failures (G) 25}} | |||
Revision as of 18:15, 14 November 2019
| ML080930025 | |
| Person / Time | |
|---|---|
| Site: | Seabrook |
| Issue date: | 04/02/2008 |
| From: | Reactor Projects Branch 3 |
| To: | |
| BURRITT, AL | |
| References | |
| Download: ML080930025 (25) | |
Text
NRC Annual Performance Assessment of Seabrook 2007 Reactor Oversight Program
Purpose of Todays Meeting
- Discuss Seabrook Plant Performance for CY 2007
- Provide FPL Energy the opportunity to respond to the NRCs Annual Performance Assessment and discuss new or existing programs to improve performance
- Provide the public an opportunity to discuss plant performance and the NRCs role in ensuring safe plant operations with the NRC staff 2
Agenda
- Introduction
- NRC Organization and Performance Goals
- Reactor Oversight Process (ROP)
- National Summary of Plant Performance
- Seabrooks Plant Performance Assessment
- FPL Energys Response and Remarks
- NRC Closing Remarks
- Break
- NRC available to address public questions 3
Region I Organization Samuel J. Collins Regional Administrator Marc J. Dapas Deputy Regional Administrator David C. Lew Marsha K. Gamberoni Director Division of Reactor Projects Director Division of Reactor Safety James W. Clifford Darrell J. Roberts Deputy Director Deputy Director Arthur L. Burritt Regional Specialists Branch Chief Seabrook Resident Inspectors William Raymond - Senior RI Project Engineers Peter Presby - RI (acting) Leonard Cline - Senior PE Joyce C. Tomlinson - PE 4
NRC Representatives
- Arthur L. Burritt, Branch Chief (610) 337-5069
- William Raymond, SRI (603) 474-3589
- Peter Presby, RI (acting)
(603) 474-3589
- Ross Moore, (in training) 5
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 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
Typical Baseline Inspection Areas
- Equipment Alignment
- Fire Protection
- Operator Response
- Radiation Release Controls
- Worker Radiation Protection
- Corrective Action Program 9
Significance Threshold Performance Indicators
Green Baseline Inspection
White May increase NRC oversight
Yellow Requires more NRC oversight
Red Requires the most NRC oversight Inspection Findings
Green Very low safety issue
White Low to moderate safety issue
Yellow Substantial safety issue
Red High safety issue 10
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 11
National Summary (at end of 2007)
Licensee Response 87 Regulatory Response 8 Degraded Cornerstone 8 Multiple/Repetitive Degraded Cornerstone 1 Unacceptable 0 Total 104 12
National Summary (at end of 2007)
Performance Indicator Results
Green 1954
White 8
Yellow 2
Red 0 Total Inspection Findings
Green 918
White 9
Yellow 2
Red 0 13
NRC 2007 Annual Assessment for Seabrook
- FPL Energy operated Seabrook in a manner that preserved public health and safety and protected the environment
- All cornerstone objectives were fully met
- Seabrook was in the Licensee Response column of the NRCs Action Matrix for all four quarters of 2007
- NRC plans baseline inspections at Seabrook for the remainder of CY 2008 14
NRC Inspection Activities at Seabrook
- 6000+ hours of inspection related activities
- 2329 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.861845e-4 months <br /> of direct inspection activities
- 2 resident inspectors on-site
- 13 Regional Specialist inspections 15
NRC Inspection Activities
- Team Inspections
- Component Design Basis team inspection
- Supplemental inspections
- Emergency Diesel Generators 16
Safety Significant PIs / Findings
- All Performance Indicators in the Reactor and Radiation Safety Areas at Seabrook remained GREEN throughout 2007
- Inspectors documented six GREEN inspection findings in the Reactor and Radiation Safety Areas at Seabrook in 2007 17
NRC Inspection Findings
- Green - Enclosure building air handling fan power supply cable connections not torqued per procedures.
- Green - Inadequate testing of the alternate cooling water supply resulted in failure of alternate cooling water to centrifugal charging pump lube oil coolers
- Green - Inadequate corrective actions resulted in multiple voltage regulator failures of the B EDG 18
NRC 2007 Assessment Summary for Seabrook
- FPL Energy operated Seabrook in a manner that preserved public health and safety and protected the environment.
- Seabrook was in the Licensee Response Column of the Action Matrix for all of 2007.
- NRC plans baseline inspections for the remainder of 2008.
19
Licensee Response and Remarks Mr. G. St. Pierre Site Vice President - Seabrook FPL Energy 20
Contacting the NRC
- Report an emergency:
(301) 816-5100 (call collect)
- Report a safety concern:
(800) 695-7403
Allegation@nrc.gov
- General information or questions:
www.nrc.gov
Select Public Meetings & Involvement or Contact Us 21
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 1-800-397-4209 (Toll Free) 22
End of the Presentation Nuclear Regulatory Commission - Region I King of Prussia, Pennsylvania March 25, 2008
NRC Performance Indicators Initiating Events PIs
- Unplanned Scrams
- Unplanned Scrams with Complications
- Unplanned Power Changes Mitigating Systems PIs
- Emergency AC Power System
- High Pressure Injection System
- Residual Heat Removal System
- Cooling Water Support Systems
- Safety System Functional Failures Barrier Integrity PIs
- Reactor Coolant System Specific Activity
- Reactor Coolant System Leakage Emergency Planning PIs
- Drill / Exercise Performance
- Emergency Response Organization Participation
- Alert and Notification System Radiation Protection PIs
- Occupational Exposure Control Effectiveness
Seabrook Performance Indicators Occupational RETS/ODCM Unplanned Emergency AC RCS Specific Drill/Exercise Security Exposure Control Radiological Scrams (G) Power System (G) Activity (G) Performance (G) (Not Public)
Effectiveness (G) Effluent (G)
Unplanned High Pressure ERO Drill Scrams with Injection System RCS Leakage (G)
Participation (G)
Complications (G) (G)
Residual Heat Alert and Unplanned Power Removal System Notification Changes (G)
(G) System (G)
Heat Removal System (G)
Cooling Water Systems (G)
Safety System Functional Failures (G) 25