ML061510554

NRC Cy 2005 Annual Assessment Meeting, BFN

ML061510554
Person / Time
Site:	Browns Ferry
Issue date:	05/02/2006
From:	NRC/RGN-II
To:
Shared Package
ML061510545	List: ML061510549 ML061510554
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Download: ML061510554 (18)

Text

NRC CY 2005 Annual Assessment Meeting BROWNS FERRY NUCLEAR PLANT Athens, Alabama May 2, 2006 Enclosure 2

Purpose of Todays Meeting z A public forum for discussion of the performance of the operating Browns Ferry units z NRC will address Browns Ferry performance issues identified in the annual assessment letter z Browns Ferry management 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 Reactor Oversight Process 3/4 Review 3/4 National Summary of Plant Performance z Browns Ferrys Plant Performance Results z Remarks 3/4 Browns Ferry Management Response and Remarks 3/4 NRC Closing Remarks z Break z NRC Available to Address Public Questions

Region II Organization William Travers Regional Administrator Loren Plisco Deputy Regional Administrator Charles Casto Victor McCree Director Division of Reactor Projects Director Division of Reactor Safety Joseph Shea Harold Christensen Deputy Director Deputy Director Malcolm Widmann Regional Specialists Branch Chief Larry Garner Thierry Ross William Bearden Heather Gepford Robert Monk Charles Stancil U2/3 Project Engineers Units 2 & 3 Edward Christnot Larry Mellen Resident Inspectors U1 Resident Inspectors Scott Shaeffer U1 Project Engineers

NRC Performance Goals PRIMARY GOALS z Ensure protection of public health and safety and the environment z Ensure the secure use and management of radioactive materials Other Goals z Ensure openness in NRC regulatory process z Ensure that NRC actions are effective, efficient, realistic, and timely z Ensure excellence in NRC management to carry out the NRCs 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 ~80 hrs/yr z Triennial Fire Protection ~200 hrs /3 yrs z Operator Response ~125 hrs/yr z Emergency Preparedness ~80 hrs/yr z Rad Release Controls ~110 hrs /2 yrs z Worker Radiation Protection ~90 hrs/yr z Corrective Action Program ~250 hrs /2 yrs z Corrective Action Case Reviews ~60 hrs/yr

Performance Thresholds Safety Significance Green: Very low safety issue White: Low-to-moderate safety issue Yellow: Substantial safety issue Red: High safety issue NRC Inspection Efforts Green: Only Baseline Inspections White: May increase NRC oversight Yellow: Increased NRC oversight Red: Increased NRC oversight and other NRC actions

Action Matrix Concept Licensee Regulatory Degraded Multiple/Rep. Unacceptable Response Response Cornerstone Degraded Performance L cen si R espn o

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Cornerstone z Increasing Safety Significance z Increasing NRC Inspection Efforts z Increasing NRC/Licensee Management Involvement z Increasing Regulatory Actions

National Summary of Plant Performance Status at End of CY 2005 Licensee Response 84 Regulatory Response 12 Degraded Cornerstone 4 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total 103

Browns Ferry CY 2005 Inspection Activities 10,900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> of inspection related activities, including:

z Radiation Protection inspections z Emergency Preparedness inspections z Problem Identification and Resolution inspection z Safety System Design and Performance inspection z Reactor Operator Requalification inspection z U2 refueling outage related inspections including in-service inspections z ISFSI dry run inspection z Unit 1 Recovery Project Inspections (over half)

Browns Ferry Unit 1 ROP Transition z In calendar year 2004, the NRC determined that the Unit 1 ROP transition criteria was met for the Occupational Radiation Safety, Public Radiation Safety, Emergency Preparedness, and Physical Protection Cornerstones.

z NRC inspections for Unit 1 in these areas were performed under the ROP during the CY 2005 assessment cycle in conjunction with Units 2 and 3 inspections.

Browns Ferry CY 2005 Assessment Results z Browns Ferrys performance was within the Licensee Response Column of the NRCs Action Matrix z All ROP inspection findings at Browns Ferry were classified as very low safety significance (Green) z All Browns Ferry performance indicators for Units 1 and 2 were Green

Browns Ferry Assessment Summary z TVA operated Browns Ferry in a manner that preserved public health and safety z All cornerstone objectives were met z NRC plans routine baseline inspections at Browns Ferry Units 2 and 3 and in the applicable cornerstones at U1 for the remainder of CY 2006

Browns Ferry CY 2006 Scheduled Inspection Activities z Resident inspector baseline inspections z Radiation Protection inspections z Emergency Preparedness inspections z Triennial Fire Protection inspection z Reactor Operator Initial inspection z Component Design Bases inspection z U3 Refueling Outage, including in-service inspection z Heat sink inspection z Modifications inspection z ISFSI inspections z Unit 1 Recovery Project inspections

NRC CY 2005 Annual Assessment Meeting BROWNS FERRY NUCLEAR PLANT Athens, Alabama May 2, 2006

Contacting the NRC z Report an emergency 3/4 (301) 816-5100 (call collect) z Report a safety concern 3/4 (800) 695-7403 3/4 Allegation@nrc.gov z General information or questions 3/4 www.nrc.gov 3/4 Select What We Do for Public Affairs

Reference Sources z Reactor Oversight Process 3/4 http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html z Public Electronic Reading Room 3/4 http://www.nrc.gov/reading-rm.html z Public Document Room 3/4 1-800-397-4209 (Toll Free)