ML051100457

NRC CY2004 Annual Assessment Meeting - Brunswick - Southport, North Carolina, April 12, 2005

ML051100457
Person / Time
Site:	Brunswick
Issue date:	04/12/2005
From:	NRC/RGN-II
To:
References
Download: ML051100457 (19)

Text

NRC CY2004 Annual Assessment Meeting BRUNSWICK Southport, North Carolina April 12, 2005

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

William Travers 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 Engineers Resident Inspectors George MacDonald Eugene DiPaolo James Polickoski Joseph Austin

NRC Performance Goals PRIMARY GOALS Ensure protection of the public health and safety and the environment Ensure 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 Triennial Fire Protection ~200 hrs every 3 yrs Operator Response ~125 hrs/yr Emergency Preparedness ~80 hrs/yr Rad Release Controls ~100 hrs every 2 yrs Worker Radiation Protection ~100 hrs/yr Corrective Action Program ~250 hrs every 2 yrs 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 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 2004 icensee Response 78 egulatory Response 21 egraded Cornerstone 0 ultiple/Repetitive Degraded Cornerstone 3 nacceptable 0 Total 102*

Davis-Besse under a special inspection process

Brunswick CY2004 Inspection Activities

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

• Licensed operator requalification inspection

• Engineering modification inspection

• Radiation protection inspections

• Maintenance inspection

• Fire protection inspection

• Emergency preparedness inspections

• Reactor operator initial exam

• Special Inspection on a loss-of-offsite power event

• Supplemental Inspection on emergency diesel generator White finding

Brunswick CY2004 Assessment Results Unit 1 performance was within the Licensee Response Column of the NRCs Action Matrix all year Unit 2 performance was within the Regulatory Response Column of he NRCs Action Matrix all year All Unit 1 inspection findings were classified as very low safety significance (Green)

One Unit 2 inspection finding was classified as low-to-moderate significance (White)

All performance indicators were Green

Unit 2 Significant White Finding Unit 2 EDG jacket water cooling leak Failure to correct leak resulted in inoperable EDG Supplemental inspection indicated corrective action was adequate

Corporate Discrimination Violation

• Discrimination against site access authorization superintendent in April 1999

• Corrective action completed in March 2004

• Issue does not apply to 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 2005

Brunswick CY2005 Inspection Activities

• Resident inspector daily inspections

• Radiation protection inspections

• Maintenance inspection

• Emergency preparedness inspections

• Problem identification and resolution inspection

• License renewal inspection

• Safety system design and performance inspection

NRC CY2004 Annual Assessment Meeting BRUNSWICK Southport, North Carolina April 12, 2005

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)