ML041190585

Meeting Summary with NRC Re Annual Assessment Meeting NRC Cy 2003 - Brunswick Steam Electric Plant

ML041190585
Person / Time
Site:	Brunswick
Issue date:	04/13/2004
From:	Fredrickson P NRC/RGN-II/DRP/RPB3
To:	Gannon C Carolina Power & Light Co
Shared Package
ML041190571	List: ML041190577 ML041190585
References
Download: ML041190585 (18)

Text

NRC CY2003 Annual Assessment Meeting BRUNSWICK Southport, North Carolina April 13, 2004 ENCLOSURE 2

Purpose of Todays Meeting

• A public forum for discussion of Brunswick performance

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

• Brunswick 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

• Introduction

• Review of Reactor Oversight Process

• National Summary of Plant Performance

• Discussion of Brunswick Plant Performance Results

• Brunswick Management Response and Remarks

• NRC Closing Remarks

• Break

• NRC Available to Address Public Questions

Region II Organization Luis Reyes Regional Administrator Loren Plisco Deputy Regional Administrator Victor McCree Charles Casto Director Division of Reactor Projects Director Division of Reactor Safety Leonard Wert Harold Christensen Deputy Director Deputy Director Paul Fredrickson Regional Specialists Branch Chief Brunswick Project Engineer Resident Inspectors George MacDonald Eugene DiPaolo Joseph Austin

NRC Performance Goals PRIMARY GOAL MAINTAIN SAFETY AND PROTECT THE ENVIRONMENT OTHER GOALS

• Enhance public confidence

• Improve effectiveness, efficiency, and realism of processes and decision making

• Reduce unnecessary regulatory burden

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 l Equipment Alignment ~92 hrs/yr l Triennial Fire Protection ~200 hrs every 3 yrs l Operator Response ~125 hrs/yr l Emergency Preparedness ~80 hrs/yr l Rad Release Controls ~100 hrs every 2 yrs l Worker Radiation Protection ~100 hrs/yr l Corrective Action Program ~240 hrs every 2 yrs l 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 Inspection 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

National Summary of Plant Performance Status at End of CY 2003 Licensee Response 75 Regulatory Response 22 Degraded Cornerstone 2 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total 102*

• Davis-Besse under a special restart inspection process

Brunswick CY2003 Inspection Activities

• 3900 hours0.0451 days <br />1.083 hours <br />0.00645 weeks <br />0.00148 months <br /> of inspection related activities

• Resident inspector daily inspections

• Reactor operations initial exam

• Safety system design inspection

• Reactor power uprate inspection

• Emergency preparedness inspection

• Maintenance inspection

• Reactor operator requal program inspection

• Radiation protection inspections

• Security inspections

• Problem Identification and Resolution Inspection

Brunswick CY2003 Assessment Results

• Plant performance was within the Licensee Response Column of the NRCs Action Matrix

• All inspection findings were classified as very low safety significance (Green). One potential low-to-moderate (White) safety issue

• All performance indicators are Green

Potential Significant Finding

• Unit 2 reactor feed pump speed controller design review

• Loss of feed pump during supply voltage transients

• Evaluated as Green in April 2004

Brunswick Annual Assessment Summary

• Progress Energy operated Brunswick in a manner that preserved public health and safety

• All cornerstone objectives were met

• NRC plans baseline inspections at Brunswick for the remainder of CY 2004

Brunswick CY2004 Inspection Activities

• Resident inspector daily inspections

• Engineering modification inspection

• Security inspection

• Radiation protection inspections

• Maintenance inspection

• Fire protection inspection

• Reactor operator initial exam

• Emergency preparedness inspections

NRC CY2003 Annual Assessment Meeting BRUNSWICK Southport, North Carolina April 13, 2004

Contacting the NRC l Report an emergency (301) 816-5100 (call collect) l Report a safety concern:

(800) 695-7403 Allegation@nrc.gov l General information or questions www.nrc.gov Select What We Do for Public Affairs

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