ML052090076

NRC CY2004 Annual Assessment Meeting Browns Ferry Nuclear Plant - Unit 2/3

ML052090076
Person / Time
Site:	Browns Ferry
Issue date:	05/24/2005
From:	Office of Nuclear Reactor Regulation
To:
References
Download: ML052090076 (18)

Text

Annual Assessment Meeting Browns Ferry Nuclear Plant - Units 2/3 Athens, AL May 24, 2005

Purpose of Todays Meeting

• A public forum for discussion of the performance of the operating Browns Ferry units

• NRC will address Browns Ferry performance issues identified in the annual assessment letter

• 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

• Does not include any Unit 1 Recovery Project Assessment - July 20, 2005 public status meeting planned in NRC Region II office in Atlanta, GA

Agenda

• Introduction

• Review of Reactor Oversight Process (ROP)

• National Summary of Plant Performance

• Discussion of Browns Ferry Plant Performance Results

• Browns Ferry Management Response and Remarks

• NRC Closing Remarks

• Break

• NRC Available to Address Public Questions

William Travers Regional Administrator Loren Plisco Deputy Regional Administrator Charles Casto Victor McCree Director Division of Reactor Projects Director Division of Reactor Safety Anne Boland Harold Christensen Acting Deputy Director Deputy Director Stephen Cahill Branch Chief Browns Ferry Project Engineers Resident Inspectors Scott Shaeffer Thierry Ross Robert Carrion William Bearden (Unit 1) Michael Pribish Robert Monk Edward Christnot

NRC Performance Goals PRIMARY GOALS Ensure protection of the public health and safety and the environment Enhance the secure use and management of radioactive materials OTHER GOALS

• Ensure openness in NRC regulatory process

• Ensure that NRC actions are effective, efficient, realistic and timely

• 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

• 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 ~250 hrs every 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 Cornerstone Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions

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*

• Davis-Besse is under a special inspection process

Inspection Activities 9000 hours0.104 days <br />2.5 hours <br />0.0149 weeks <br />0.00342 months <br /> of inspection related activities, including:

• Licensed operator requalification inspection

• Radiation protection inspections

• Engineering modification inspection

• ISFSI pre-operational inspections

• Emergency preparedness inspections

• Heat sink performance inspection

• License renewal inspection

• Unit 1 Recovery Project Inspections (large contribution - over half)

CY2004 Assessment Results

• Unit 2 and 3 performance was within the Licensee Response Column of the NRCs Action Matrix.

• All Unit 2 and 3 inspection findings were classified as very low safety significance (Green).

• All Unit 2 and 3 performance indicators were Green

ROP Transition

• 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.

• NRC inspections for Unit 1 in these areas will be performed under the ROP during the current assessment cycle in conjunction with Units 2 and 3 inspections.

Summary

• TVA operated Browns Ferry in a manner that preserved public health and safety

• All cornerstone objectives were met

• NRC plans baseline inspections at Browns Ferry Units 2 and 3 for the remainder of CY 2005

Inspection Activities

• Resident inspector daily inspections

• Radiation protection inspections

• Emergency preparedness exercise inspections

• Problem identification and resolution inspection

• Safety system design and performance inspection

• ISFSI pre-operational inspection

• Unit 2 outage-related in-service inspections

• License renewal inspections

• Unit 1 Recovery Project Inspections

Annual Assessment Meeting Browns Ferry Management Response and Remarks

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)