ML071290248

NRC Presentation EOC Public Meeting Slides

ML071290248
Person / Time
Site:	Byron
Issue date:	05/08/2007
From:	NRC/RGN-III
To:
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Download: ML071290248 (20)

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Byron Annual Assessment Meeting Reactor Oversight Program - CY 2006 Nuclear Regulatory Commission - Region III Byron, IL May 8, 2007

Purpose of Todays Meeting z Provide a public forum for discussion of the licensees performance z NRC will address the licensee performance issues identified in the annual assessment letter z 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 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

Region III Organization James Caldwell Regional Administrator Geoff Grant Deputy Regional Administrator Mark Satorius Cynthia Pederson Director Division of Reactor Projects (DRP) Director Division of Reactor Safety (DRS)

Steve West Anne Boland Deputy Director Deputy Director Richard Skokowski Regional Specialists Branch Chief Byron Project Engineer Resident Inspectors Desiree Smith Bruce Bartlett Raymond Ng

NRC Representatives z Bruce Bartlett, Senior Resident Inspector

- (815) 234-5451 z Raymond Ng, Resident Inspector

- (815) 234-5451 z Richard Skokowski, Branch Chief, DRP

- (630) 829-9620

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 NRCs strategic objectives

Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Baseline Inspection Performance Indicator Results Results Significance Significance Threshold Threshold Action Matrix Regulatory Response

Significance Threshold Performance Indicators Green: Baseline Inspection only 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 2006 Licensee Response 70 Regulatory Response 24 Degraded Cornerstone 6 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total 103

National Summary z Performance Indicator Results (at end of CY 2006)

Green 1843 White 11 Yellow 0 Red 0 z Total Inspection Findings (CY 2006)

Green 676 White 13 Yellow 0 Red 0

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

Byron Assessment Results (Jan 1 - Dec 31, 2006) z Safety performance for the 4th quarter at Byron Unit 1 was within the Licensee Response column of the NRC Action Matrix. For the 4th quarter Byron Unit 2 was within the Regulatory Response column of the NRC Action Matrix.

z Unit 2 was within the Regulatory Response column due to the White Performance Indicator in the Mitigating Systems cornerstone.

Safety Significant Findings or PIs z No safety significant findings were identified during this assessment period.

z A White Performance Indicator in the Mitigating Systems Performance Index (MSPI) was identified.

z On February 9, 2007, the NRC completed a supplemental inspection pursuant to Inspection Procedure 95001 due to the White Performance Indicator in the Mitigating Systems conrnerstone. No findings of significance were identified.

Byron Inspection Activities (Jan 1 - Dec 31, 2006) z 10 findings during this assessment period 6 in mitigating systems 2 in barrier integrity 1 in occupational radiation safety 1 in public radiation safety z One additional finding was evaluated separately using the traditional enforcement process

Byron Inspection Activities (Jan 1 - Dec 31, 2006) z Supplemental Inspection 95001 was completed on February 9, 2007 z Unit 1 had a refueling outage from September 10 -

October 23, 2006.

z Unit 2 operated at or near full power throughout this inspection period with minor exceptions.

Byron Annual Assessment Summary (Jan 1 - Dec 31, 2006) z Exelon Nuclear operated Byron Units 1 & 2 in a manner that preserved public health and safety z All cornerstone objectives were met with only one White Performance Indicator identified for Unit 2 Heat Removal System MSPI (Auxiliary Feedwater System) z NRC plans baseline inspections at Byron for the remainder of the assessment period. A supplemental 95001 inspection was completed on February 9, 2007.

Licensee Response and Remarks David Hoots Site Vice President Byron Generating Station

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 About NRC > Organization and Functions 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)