ML061040587

Public Meeting with Exelon Generation Company LaSalle County Station Units 1 & 2, Reactor Oversight Program - Cy 2005, NRC Presentation Slides

ML061040587
Person / Time
Site:	LaSalle
Issue date:	04/06/2006
From:	NRC/RGN-III
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Download: ML061040587 (20)

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LaSalle Annual Assessment Meeting Reactor Oversight Program - CY 2005 Nuclear Regulatory Commission - Region III Seneca, Illinois April 6, 2006

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 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

Agenda Introduction Review of Reactor Oversight Process National Summary of Plant Performance Discussion of Plant Performance Results Licensee Response and Remarks NRC Closing Remarks Break NRC available to address public questions

James Caldwell Regional Administrator Geoffrey Grant Deputy Regional Administrator Mark Satorius Cynthia Pederson Director Division of Reactor Projects Director Division of Reactor Safety Steven West Anne Boland Deputy Director Deputy Director Bruce Burgess Regional Specialists Branch Chief LaSalle Project Engineers Resident Inspectors Nirodh Shah Daniel Kimble Stuart Sheldon Douglas Eskins

NRC Representatives Mark Satorius, Director, Division Reactor Projects

- (630) 829-9600 Steven West, Deputy Division Director, DRP

- (630) 829-9601 Stephen Sands, Project Manager, NRR

- (301) 415-3154 Daniel Kimble, Senior Resident Inspector

- (815) 357-8611 Douglas Eskins, Resident Inspector

- (815) 357-8611 Bruce Burgess, Branch Chief

- (630) 829-9629 Nirodh Shah, Project Engineer

- (630) 829-9821 Stuart Sheldon, Reactor Engineer

- (630) 829-9727

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 Equipment Alignment ~80 hrs/yr Triennial Fire Protection ~200 hrs every 3 yrs Operator Response ~125 hrs/yr Emergency Preparedness ~80 hrs/yr Rad Release Controls ~110 hrs every 2 yrs Worker Radiation Protection ~90 hrs/yr Corrective Action Program ~250 hrs every 2 yrs Corrective Action Case Reviews ~60 hrs/yr

Significance Threshold Performance Indicators 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 ncreasing Safety Significance ncreasing NRC Inspection Efforts ncreasing NRC/Licensee Management Involvement ncreasing Regulatory Actions

National Summary of Plant Performance Status at End of CY 2005 icensee Response 84 egulatory Response 12 egraded Cornerstone 4 ultiple/Repetitive Degraded Cornerstone 3 nacceptable 0 Total 103

National Summary Performance Indicator Results (at end of CY 2005)

Green 1850 White 4 Yellow 0 Red 0 Total Inspection Findings (CY 2005)

Green 849 White 10 Yellow 1 Red 0

LaSalle Assessment Results (Jan 1 - Dec 31, 2005)

Licensee Response Column of Action Matrix with all Green PIs and nspection findings except for two issues.

95001 Supplemental Inspection for the 4160 VAC Design Issue Was Completed In January 2006 With No Findings 95001 was performed in October 2005 for the performance indicator ssue resulting in one finding of very low safety significance.

A Substantive Cross-Cutting Issue in the Area of Human Performance was Closed

Safety Significant Findings or PIs White -- A design deficiency in a metering circuit for the sites normal 4160 VAC offsite power supply.

• IP95001 supplemental inspection completed (Jan 2006)

• Determined to be an original design issue

• Not counted towards response columns White -- Unit 2 performance indicator for scrams with a loss of normal heat removal

• A Unit 2 scram on April 6, 2001, has been reclassified as a scram with a loss of normal heat removal.

• Historically White during the 3rd and 4th Quarters of 2003, and the 1st Quarter of 2004.

LaSalle Inspection Activities (Jan 1 - Dec 31, 2005)

There were approximately 5147 hours0.0596 days <br />1.43 hours <br />0.00851 weeks <br />0.00196 months <br /> of inspection related activities performed at LaSalle during 2005.

The inspections were performed by the Resident Inspectors and Regional Inspectors. The Regional Inspectors included specialists in Security, Emergency Preparedness, and Radiation Protection.

There were 22 Green or SL-IV Inspection Findings identified during 2005 in addition to the White finding.

There was a Refueling Outage on Unit 2 during 2005.

LaSalle Inspection Activities (Jan 1 - Dec 31, 2005)

Major team inspections performed in 2005

• Problem Identification and Resolution

• Safety System Design and Performance Capability

• Modifications/10CFR50.59

• Triennial Fire Protection

LaSalle Annual Assessment Summary January 1 - December 31, 2005 Exelon operated LaSalle in a manner that preserved public health and safety All cornerstone objectives were met with only one White finding identified (Original design issue)

NRC plans baseline inspections at LaSalle for the remainder of the assessment period

Licensee Response and Remarks Susan Landahl Site Vice President Exelon - LaSalle Station

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 What We Do for Public Affairs

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)