ML041130372

Public Meeting Licensee'S Slides, Braidwood 2003 End-of-Cycle Assessment

ML041130372
Person / Time
Site:	Braidwood
Issue date:	04/15/2004
From:	NRC/RGN-III
To:
References
Download: ML041130372 (1)

Text

Braidwood Station Annual Assessment Meeting Reactor Oversight Program - CY 2003 Nuclear Regulatory Commission - Region III Braidwood, Illinois April 15, 2004

Agenda l Introduction l Review of Reactor Oversight Process l National Summary of Plant Performance l Discussion of Plant Performance Results l Licensee Response and Remarks l NRC Closing Remarks l Break l NRC available to address public questions

NRC Representatives l Patrick Hiland, Deputy Division Director, DRP

- (630) 829-9601 l Ann Marie Stone, Branch Chief

- (630) 829-9729 l Steven Ray, Senior Resident Inspector

- (815) 458-2852 l Nirodh Shah, Resident Inspector

- (815) 458-2852

Region III Organization James Caldwell Regional Administrator Geoffrey Grant Deputy Regional Administrator Steven A. Reynolds Cynthia D. Pederson Acting Director Division of Reactor Projects Director Division of Reactor Safety Patrick Hiland Roy Caniano Acting Deputy Director Deputy Director Ann Marie Stone Regional Specialists Branch Chief Braidwood Resident Inspectors Project Engineer Steven Ray Thomas Tongue Nirodh Shah

NRC Performance Goals l Maintain safety and protect the environment l Enhance public confidence l Improve effectiveness, efficiency, and realism of processes and decision making l 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 ~200 hrs every 2 yrs l Corrective Action Case Reviews ~60 hrs/yr

Significance Threshold Performance Indicators Green: Only Baseline Inspection White: May increase NRC oversight Yellow: Requires more NRC oversight Red: Requires more NRC oversight Inspection Findings Green: Very Low safety issue White: Low to moderate safety issue Yellow: Substantial safety issue Red: High safety issue

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

Purpose of Todays Meeting n A public forum for discussion of the licensees performance n NRC will address the licensee performance issues identified in the annual assessment letter n Licensee will respond to the information in the letter and inform the NRC of new or existing programs to maintain or improve their performance

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 is in IMC 0350 process

National Summary l Performance Indicator Results (at end of CY 2003)

Green 1825 White 15 Yellow 0 Red 0 l Total Inspection Findings (CY 2003)

Green 748 White 9 Yellow 2 Red 1

Braidwood Assessment Results (Jan 1 - Dec 31, 2003) n Unit 1: Regulatory Response Column l All Findings were categorized as very low safety significance (Green) l One Performance Indicator was within the White band l Unit 2: Licensee Response Column l All Findings were categorized as very low safety significance (Green) l All Performance Indicators were within the Green band

Mitigating System Unavailability Auxiliary Feedwater System - Unit 1 n Changed from Green to White between the first and second quarter of 2003 and remained White for remainder of year.

• Governor oil level concerns in second quarter

• Turbo charger blower problems in the third quarter n Supplemental Inspection 95001 will be conducted per the Action Matrix.

Braidwood Inspection Activities (Jan 1 - Dec 31, 2003) n Completed Baseline Inspections - 2285hours

• Routine Integrated Inspections

• Triennial Fire Protection

• Engineering Plant Design

• Identification and Resolution of Problems n Unit 1 and Unit 2 Refueling Outages

Braidwood Inspection Activities (Jan 1 - Dec 31, 2004) n Refueling Outage - Unit 1 n Major team inspections

• Emergency Preparedness Exercise n Supplemental Inspection

• Auxiliary Feedwater System, Unit 1 - April 2004

Braidwood Annual Assessment Summary January 1 - December 31, 2003 l Exelon operated Braidwood Units 1 & 2 in a manner that preserved public health and safety l All cornerstone objectives were met with only one White performance indicator in the Mitigating System Cornerstone l NRC plans baseline inspections at Braidwood for the remainder of the assessment period and a supplemental inspection of the Unit 1 Auxiliary Feedwater System

Licensee Response and Remarks 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)