Public Meeting NRC Slides DC Cook End-of-Cycle Plant Performance AssessmentML051260391 |
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Cook |
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04/21/2005 |
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NRC/RGN-III |
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Download: ML051260391 (19) |
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Category:Meeting Briefing Package/Handouts
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[Table view] |
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D. C. Cook Annual Assessment Meeting Reactor Oversight Program - CY 2004 Nuclear Regulatory Commission - Region III Lisle, IL April 21, 2005
Agenda z Introduction z Review of Reactor Oversight Process z National Summary of Plant Performance z Discussion of Plant Performance Results z Licensee Response and Remarks z NRC Closing Remarks z Break z NRC available to address public questions
Purpose of Todays Meeting A public forum for discussion of the licensees performance NRC will address the licensee performance issues identified in the annual assessment letter Licensee will respond to the information in the letter and inform the NRC of new or existing programs to maintain or improve their performance
NRC Representatives z Mark A. Satorius, Director, Division Reactor Projects
- (630) 829-9600 z Steven A. Reynolds, Deputy Division Director, DRP
- (630) 829-9601 z C. Fred Lyon, Project Manager, NRR
- (301) 415-2296 z Brian Kemker, Senior Resident Inspector
- (269) 465-5353 z Robert M. Lerch, Senior Project Engineer (Acting Branch Chief)
- (630) 829-9759 z Eric R. Duncan, Branch Chief
- (630) 829-9628
Region III Organization James L. Caldwell Regional Administrator Geoffrey E. Grant Deputy Regional Administrator Mark A. Satorius Cynthia D. Pederson Director Division of Reactor Projects Director Division of Reactor Safety Steven A. Reynolds Roy J. Caniano Deputy Director Deputy Director Robert M. Lerch Regional Specialists Branch Chief Acting for Eric Duncan D. C. Cook Resident Inspectors Project Engineer Brian Kemker Robert M. Lerch Frances Ramirez
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 ~92 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 ~100 hrs every 2 yrs z Worker Radiation Protection ~100 hrs/yr z Corrective Action Program ~200 hrs every 2 yrs z Corrective Action Case Reviews ~60 hrs/yr
Significance Threshold Performance Indicators (PIs)
Green: Only 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 2004 Licensee Response 78 Regulatory Response 21 Degraded Cornerstone 0 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total 102*
National Summary z Performance Indicator Results (at end of CY 2004)
Green 1834 White 6 Yellow 0 Red 0 z Total Inspection Findings (CY 2004)
Green 778 White 11 Yellow 0 Red 0
D.C. Cook Assessment Results (Jan 1 - Dec 31, 2004) z Unit 1:
z Regulatory Response Column - Based on one White inspection finding in the Public Radiation Safety cornerstone (shared by both units).
z Unit 2:
z Q1/2004: Degraded Cornerstone Column - Based on two White PIs in the Initiating Events cornerstone and the one White inspection finding from above.
z Q2-Q4/2004: Regulatory Response Column - Plant performance exited the Degraded Cornerstone Column when one White PI transitioned to Green.
z Supplemental Inspections conducted:
z IP 95002 reviewed the two White performance indicators of Unit 2 and determined that the licensee conducted an adequate root cause evaluation.
z IP 95001 reviewed the circumstances surrounding the one White inspection finding and determined that the licensee conducted an adequate root cause evaluation.
D.C. Cook Inspection Activities (Jan 1 - Dec 31, 2004) 1818 hours0.021 days <br />0.505 hours <br />0.00301 weeks <br />6.91749e-4 months <br /> of total baseline inspection by resident and regional inspectors.
7 Green findings in the Reactor Safety and Radiation Safety Strategic Performance Areas.
Unit 2 Cycle 15 refueling outage October 2 -
November 9, 2004.
D.C. Cook Inspection Activities (Jan 1 - Dec 31, 2004)
IP 95001 and 95002 Supplemental Inspections Biennial Safety System Design and Performance Capability Inspection Inservice Inspection and Radiation Protection Inspection performed during refueling outage Biennial Permanent Plant Modifications and 10 CFR 50.59 Inspection Problem Identification and Resolution Inspection License Renewal related inspections Maintenance Rule implementation inspection
D.C. Cook Annual Assessment Summary January 1 - December 31, 2004 z AEP operated D.C. Cook Units 1 & 2 in a manner that preserved public health and safety.
z NRC plans baseline inspections at D.C. Cook for calendar year 2005.
Licensee Response and Remarks Mano Nazar Senior Vice President Chief Nuclear Officer D.C. Cook
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
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)