ML071150327

Brunswick, EOC Slides, Cy 2006

ML071150327
Person / Time
Site:	Brunswick
Issue date:	04/23/2007
From:	NRC/RGN-II
To:
References
Download: ML071150327 (20)

Text

NRC CY2006 Annual Assessment Meeting BRUNSWICK Southport, North Carolina April 23, 2007

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 William Travers Regional Administrator Victor McCree Deputy Regional Administrator Charles Casto Joseph Shea Director, Division of Reactor Projects Director, Division of Reactor Safety Harold Christensen Kriss Kennedy Deputy Director Deputy Director Randall Musser Regional Specialists Branch Chief Brunswick Project Engineer Resident Inspectors Son Ninh Eugene DiPaolo, SRI Joseph Austin, RI

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 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 Rad 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

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

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

Brunswick CY2006 Inspection Activities

• 5361 hours0.062 days <br />1.489 hours <br />0.00886 weeks <br />0.00204 months <br /> of inspection related activities

• Maintenance inspection

• Engineering modification inspection

• Engineering design bases inspection

• Supplemental Inspection

• Radiation protection inspections

• Emergency preparedness inspections

• Licensed operator requalification inspection

Brunswick CY2006 Assessment Results

• Both Brunswick units were in the Regulatory Response Column of the NRCs Action Matrix due to the Mitigating Systems Performance Index, Emergency AC Power System PI crossing the Green/White threshold to White in the 2nd quarter of CY2006. This White PI, involving the Mitigating System Cornerstone, reflected performance at a level requiring increased regulatory response. A Supplemental Inspection of Unit 1 and 2 activities, using Inspection Procedure (IP) 95001, Inspection for One or Two White Inputs in a Strategic Performance Area, as required by the NRCs Action Matrix was commenced in the fall 2006.

This inspection was suspended due to an emergent failure of Emergency Diesel Generator #1 on November 2, 2006.

Because this additional failure had a negative impact on the PI, completion of the inspection was delayed pending the final determination of significance. NRC completed the Supplemental Inspection (95001) in April, 2007.

Brunswick CY2006 Assessment Results

• Brunswick Unit 2 was in the Regulatory Response Column during the 1st quarter of CY 2006. Brunswick Unit 2 had crossed the Green/White threshold for the Unplanned Power Changes per 7000 Critical Hours PI during the 4th quarter of CY 2005. The PI, involving the Initiating Events Cornerstone, remained White through the 1st quarter of CY2006 and returned to Green in the 2nd quarter of CY 2006. A Supplemental Inspection using IP 95001 was conducted in June 2006 for the White PI and no findings of significance were identified.

Brunswick Year to Date Performance On April 20, 2007, the NRC issued a white finding for EDG #1 being inoperable for a period in excess of that allowed by Technical Specifications.

This finding, coupled with the white performance indicator previously discussed, places Brunswick Unit 1 in Column 3, or the Degraded Cornerstone Column of the NRCs Action Matrix. This will result in the NRC performing a 95002 supplemental inspection.

95002 Supplemental Inspection This inspection procedure is conducted to provide assurance that the root and contributing causes for the individual and collective risk significant performance issues are understood, to independently assess the extent of condition, to independently determine if safety culture components caused or significantly contributed to the risk significant performance issues, and to provide assurance that the corrective actions are sufficient to prevent recurrence.

Brunswick 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 CY2007. A supplemental inspection will be performed in CY2007.

Brunswick CY2007 Scheduled Inspection Activities

• Resident inspector daily inspections

• Heat sink inspection

• Problem identification and resolution

• Radiation protection inspections

• Inservice inspection

• Licensed operator initial examination

• Component design bases inspection

• Emergency preparedness inspection

NRC CY2006 Annual Assessment Meeting BRUNSWICK Southport, North Carolina April 23, 2007

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)