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| number = ML070940496 | | number = ML070940496 | ||
| issue date = 03/02/2007 | | issue date = 03/02/2007 | ||
| title = | | title = Meeting Slides - Palisades Annual Assessment Meeting, CY2006 Reactor Oversight Program | ||
| author name = | | author name = | ||
| author affiliation = NRC/RGN-III/DRMA, NRC/RGN-III/DRP | | author affiliation = NRC/RGN-III/DRMA, NRC/RGN-III/DRP | ||
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=Text= | =Text= | ||
{{#Wiki_filter:Palisades Annual Assessment | {{#Wiki_filter:Palisades Annual Assessment Meeting CY2006 Reactor Oversight Program South Haven, MI April 11, 2007 | ||
issues identified in the annual assessment | urpose of Todays Meeting A public forum for discussion of the licensees performance NRC will discuss the licensee performance issues identified in the annual assessment letter Licensee will be given the opportunity to respond to the information in the letter and inform the NRC of new or existing programs to maintain or improve their performance | ||
genda Introduction Review of the Reactor Oversight Process National Summary of Plant Performance Discussion of Palisades Plant Performance Licensee Response and Remarks NRC Closing Remarks Break NRC available to address public questions | |||
Region III Organization James L. Caldwell Regional Administrator Geoffrey E. Grant Deputy Regional Administrator Mark A Satorius Cynthia D. Pederson DRP Division Director Director, Division of Reactor Safety K. Steven West Anne T. Boland DRP Deputy Division Director Deputy Director Christine A. Lipa Regional Specialists Branch Chief Robert Lerch, Project Engineer Palisades Nuclear Plant Alexander Garmoe, Reactor Engineer Gregory Kolcum, Reactor Engineer John Ellegood, Senior Resident Inspector Adam Wilson, Reactor Engineer John Giessner, Resident Inspector Frank Tran, Reactor Engineer | |||
NRC Representatives Christine A. Lipa, Branch Chief (630) 829-9619 John A. Ellegood, Senior Resident Inspector (269) 764-8971 John (Jack) B. Giessner, Resident Inspector (269) 764-8971 Mahesh L. Chawla, Project Manager, NRR (Headquarters) | |||
(301) 415-8371 | |||
NRC Performance Goals Safety: Ensure protection of public health and safety and the environment Security: Ensure the secure use and management of radioactive materials Openness: Ensure openness in our regulatory process Effectiveness: Ensure that NRC actions are effective, efficient, realistic, and timely Management: Ensure excellence in agency management to carry out the NRCs strategic objective | |||
Reactor Oversight Process 3 Strategic Performance Areas are divided into 7 Cornerstones of Safety Findings and Performance Indicators are assigned a Cornerstone Findings can be assigned a cross-cutting aspect, which is a causal factor for the performance deficiency Substantive Cross-Cutting Issues can be determined if there are numerous findings with a common cross-cutting aspect or theme Human Performance, Problem Identification and Resolution, and Safety Conscious Work Environment | |||
Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Baseline Inspection Performance Indicator Performance Indicator Results Results Results Significance Significance Significance Threshold Threshold Threshold Action ActionMatrix Matrix Regulatory Response | |||
Regulatory Response | |||
aseline Inspection Examples Post Maintenance Testing ~80 hrs annual Equipment Alignment ~80 hrs annual Triennial Fire Protection ~200 hrs triennial Operator Response ~125 hrs annual Emergency Preparedness ~80 hrs annual Radiation Release Controls ~110 hrs biennial Occupational Radiation Protection ~90 hrs annual Corrective Action Program Review ~250 hrs biennial Corrective Action Case Reviews ~60 hrs annual Design Basis Inspections ~400 hrs biennial | |||
ignificance Threshold Performance Indicators Green: Implement Baseline Inspection program White: Increase NRC oversight with 95001 inspection Yellow: | |||
Yellow Increase NRC oversight with 95002 inspection Red: Increase NRC oversight with 95003 inspection Inspection Findings Green: Very Low safety significance White: Low to Moderate safety significance (95001) | |||
Yellow: | |||
Yellow Substantial safety significance (95002) | |||
Red: High safety significance (95003) | |||
Palisades for the CY2007 assessment | ction Matrix Licensee Regulatory Degraded Multiple/Rep. Unacceptable Response Response Cornerstone Degraded Performance Cornerstone Increased safety significance of findings and performance indicators results in movement to the right Movement to the right results in: | ||
Additional NRC inspections Increased Management Involvement Increased Regulatory Actions | |||
National Plant Performance Status at End of CY 2006 Licensee Response 70 Regulatory Response 24 Degraded Cornerstone 6 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total 103 | |||
National Plant Performance Performance Indicator Results (end of CY 2006) | |||
Green: 1843 White: 11 Yellow: | |||
Yellow 0 Red: 0 Total Inspection Findings (CY 2006) | |||
Green: 676 White: 13 Yellow: | |||
Yellow 0 Red: 0 | |||
alisades Assessment Activities January 1 - December 31, 2006 | |||
* Refueling Outage March 31 - May 10 | |||
- Began one day early due to Tech Spec required shutdown for valve failure in HPSI system that led to White MSPI | |||
- In-core cask momentarily surfaced in refueling cavity that led to NRC Special Inspection | |||
* Component Design Basis Team Inspection conducted November 13 - December 15, 2006 (IR 2006-009) | |||
* Problem Identification and Resolution Biennial Inspection conducted January 30 - February 17 (IR 2006-003) | |||
alisades Assessment Results 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Licensee Regulatory Licensee Licensee Response Response Response Response Regulatory Response Column in 2nd Quarter due to a White High Pressure Safety Injection (HPSI) mitigating systems performance indicator (MSPI) | |||
The performance indicator returned to Green during the 3rd Quarter No Substantive Cross-Cutting Issues identified Regulatory Actions 27 Green Findings and Non-Cited Violations (NCV) 1 Severity Level IV NCV 1 White performance indicator | |||
afety Significant Issues 2 Special Inspections Conducted April 2006 when an in-core cask momentarily rose to the surface of the refueling cavity November 2006 when the NRC discovered all three AFW pumps in manual control when required to be in automatic 95001 inspection regarding White HPSI MSPI conducted in February 2007 (not part of CY2006 assessment) | |||
nnual Assessment Summary January 1 - December 31, 2006 NMC operated Palisades in a manner that preserved public health and safety All cornerstone objectives were met with one White performance indicator identified NRC has planned baseline inspections at Palisades for the CY2007 assessment period Triennial Fire Protection inspection scheduled for May 7 - May 25, 2007 | |||
ontacting the NRC For general information or questions: | |||
www.nrc.gov Select What We Do for Public Affairs To report a safety concern: | |||
(800) 695-7403 Allegation@nrc.gov To report an emergency: | |||
(301) 816-5100 (call collect) | |||
eference 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) | |||
icensee Remarks Palisades Representatives | |||
Palisades Annual Assessment Meeting CY2006 Reactor Oversight Program Questions and Comments from members of the public Information on the NRC and our assessment processes is available at this meeting. We encourage you to take copies of this information home with you.}} |
Latest revision as of 12:58, 7 December 2019
ML070940496 | |
Person / Time | |
---|---|
Site: | Palisades |
Issue date: | 03/02/2007 |
From: | NRC/RGN-III/DRMA, Division Reactor Projects III |
To: | |
References | |
Download: ML070940496 (21) | |
Text
Palisades Annual Assessment Meeting CY2006 Reactor Oversight Program South Haven, MI April 11, 2007
urpose of Todays Meeting A public forum for discussion of the licensees performance NRC will discuss the licensee performance issues identified in the annual assessment letter Licensee will be given the opportunity to respond to the information in the letter and inform the NRC of new or existing programs to maintain or improve their performance
genda Introduction Review of the Reactor Oversight Process National Summary of Plant Performance Discussion of Palisades Plant Performance Licensee Response and Remarks NRC Closing Remarks Break NRC available to address public questions
Region III Organization James L. Caldwell Regional Administrator Geoffrey E. Grant Deputy Regional Administrator Mark A Satorius Cynthia D. Pederson DRP Division Director Director, Division of Reactor Safety K. Steven West Anne T. Boland DRP Deputy Division Director Deputy Director Christine A. Lipa Regional Specialists Branch Chief Robert Lerch, Project Engineer Palisades Nuclear Plant Alexander Garmoe, Reactor Engineer Gregory Kolcum, Reactor Engineer John Ellegood, Senior Resident Inspector Adam Wilson, Reactor Engineer John Giessner, Resident Inspector Frank Tran, Reactor Engineer
NRC Representatives Christine A. Lipa, Branch Chief (630) 829-9619 John A. Ellegood, Senior Resident Inspector (269) 764-8971 John (Jack) B. Giessner, Resident Inspector (269) 764-8971 Mahesh L. Chawla, Project Manager, NRR (Headquarters)
(301) 415-8371
NRC Performance Goals Safety: Ensure protection of public health and safety and the environment Security: Ensure the secure use and management of radioactive materials Openness: Ensure openness in our regulatory process Effectiveness: Ensure that NRC actions are effective, efficient, realistic, and timely Management: Ensure excellence in agency management to carry out the NRCs strategic objective
Reactor Oversight Process 3 Strategic Performance Areas are divided into 7 Cornerstones of Safety Findings and Performance Indicators are assigned a Cornerstone Findings can be assigned a cross-cutting aspect, which is a causal factor for the performance deficiency Substantive Cross-Cutting Issues can be determined if there are numerous findings with a common cross-cutting aspect or theme Human Performance, Problem Identification and Resolution, and Safety Conscious Work Environment
Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Baseline Inspection Performance Indicator Performance Indicator Results Results Results Significance Significance Significance Threshold Threshold Threshold Action ActionMatrix Matrix Regulatory Response
aseline Inspection Examples Post Maintenance Testing ~80 hrs annual Equipment Alignment ~80 hrs annual Triennial Fire Protection ~200 hrs triennial Operator Response ~125 hrs annual Emergency Preparedness ~80 hrs annual Radiation Release Controls ~110 hrs biennial Occupational Radiation Protection ~90 hrs annual Corrective Action Program Review ~250 hrs biennial Corrective Action Case Reviews ~60 hrs annual Design Basis Inspections ~400 hrs biennial
ignificance Threshold Performance Indicators Green: Implement Baseline Inspection program White: Increase NRC oversight with 95001 inspection Yellow:
Yellow Increase NRC oversight with 95002 inspection Red: Increase NRC oversight with 95003 inspection Inspection Findings Green: Very Low safety significance White: Low to Moderate safety significance (95001)
Yellow:
Yellow Substantial safety significance (95002)
Red: High safety significance (95003)
ction Matrix Licensee Regulatory Degraded Multiple/Rep. Unacceptable Response Response Cornerstone Degraded Performance Cornerstone Increased safety significance of findings and performance indicators results in movement to the right Movement to the right results in:
Additional NRC inspections Increased Management Involvement Increased Regulatory Actions
National Plant Performance Status at End of CY 2006 Licensee Response 70 Regulatory Response 24 Degraded Cornerstone 6 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total 103
National Plant Performance Performance Indicator Results (end of CY 2006)
Green: 1843 White: 11 Yellow:
Yellow 0 Red: 0 Total Inspection Findings (CY 2006)
Green: 676 White: 13 Yellow:
Yellow 0 Red: 0
alisades Assessment Activities January 1 - December 31, 2006
- Refueling Outage March 31 - May 10
- Began one day early due to Tech Spec required shutdown for valve failure in HPSI system that led to White MSPI
- In-core cask momentarily surfaced in refueling cavity that led to NRC Special Inspection
- Component Design Basis Team Inspection conducted November 13 - December 15, 2006 (IR 2006-009)
- Problem Identification and Resolution Biennial Inspection conducted January 30 - February 17 (IR 2006-003)
alisades Assessment Results 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Licensee Regulatory Licensee Licensee Response Response Response Response Regulatory Response Column in 2nd Quarter due to a White High Pressure Safety Injection (HPSI) mitigating systems performance indicator (MSPI)
The performance indicator returned to Green during the 3rd Quarter No Substantive Cross-Cutting Issues identified Regulatory Actions 27 Green Findings and Non-Cited Violations (NCV) 1 Severity Level IV NCV 1 White performance indicator
afety Significant Issues 2 Special Inspections Conducted April 2006 when an in-core cask momentarily rose to the surface of the refueling cavity November 2006 when the NRC discovered all three AFW pumps in manual control when required to be in automatic 95001 inspection regarding White HPSI MSPI conducted in February 2007 (not part of CY2006 assessment)
nnual Assessment Summary January 1 - December 31, 2006 NMC operated Palisades in a manner that preserved public health and safety All cornerstone objectives were met with one White performance indicator identified NRC has planned baseline inspections at Palisades for the CY2007 assessment period Triennial Fire Protection inspection scheduled for May 7 - May 25, 2007
ontacting the NRC For general information or questions:
www.nrc.gov Select What We Do for Public Affairs To report a safety concern:
(800) 695-7403 Allegation@nrc.gov To report an emergency:
(301) 816-5100 (call collect)
eference 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)
icensee Remarks Palisades Representatives
Palisades Annual Assessment Meeting CY2006 Reactor Oversight Program Questions and Comments from members of the public Information on the NRC and our assessment processes is available at this meeting. We encourage you to take copies of this information home with you.