ML041130372
| ML041130372 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 04/15/2004 |
| From: | NRC/RGN-III |
| To: | |
| References | |
| Download: ML041130372 (1) | |
Text
Braidwood Station Braidwood Station Annual Assessment Meeting Annual Assessment Meeting Reactor Oversight Program - CY 2003 Reactor Oversight Program - CY 2003 Nuclear Regulatory Commission - Region III Nuclear Regulatory Commission - Region III Braidwood, Illinois Braidwood, Illinois April 15, 2004 April 15, 2004
Agenda
Introduction
Review of Reactor Oversight Process
National Summary of Plant Performance
Discussion of Plant Performance Results
Licensee Response and Remarks
NRC Closing Remarks
Break
NRC available to address public questions
NRC Representatives NRC Representatives
Patrick Hiland, Deputy Division Director, DRP
- (630) 829-9601
Ann Marie Stone, Branch Chief
- (630) 829-9729
Steven Ray, Senior Resident Inspector
- (815) 458-2852
Nirodh Shah, Resident Inspector
- (815) 458-2852
Region III Organization James Caldwell Regional Administrator Geoffrey Grant Deputy Regional Administrator Steven A. Reynolds Acting Director Division of Reactor Projects Patrick Hiland Acting Deputy Director Cynthia D. Pederson Director Division of Reactor Safety Roy Caniano Deputy Director Ann Marie Stone Branch Chief Regional Specialists Braidwood Resident Inspectors Steven Ray Nirodh Shah Project Engineer Thomas Tongue
NRC Performance Goals
Maintain safety and protect the environment
Enhance public confidence
Improve effectiveness, efficiency, and realism of processes and decision making
Reduce unnecessary regulatory burden
Reactor Oversight Process Safety Cornerstones Baseline Inspection Results Significance Threshold Action Matrix Significance Threshold Performance Indicator Results Regulatory Response Strategic Performance Areas Safety Cornerstones Baseline Inspection Results Significance Threshold Action Matrix Significance Threshold Performance Indicator Results Regulatory Response Strategic Performance Areas
Examples of Baseline Inspections
Equipment Alignment
~92 hrs/yr
Triennial Fire Protection
~200 hrs every 3 yrs
Operator Response
~125 hrs/yr
~80 hrs/yr
Rad Release Controls
~100 hrs every 2 yrs
Worker Radiation Protection ~100 hrs/yr
Corrective Action Program
~200 hrs every 2 yrs
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
Response
Regulatory
Response
Degraded Cornerstone Multiple/Rep.
Degraded Cornerstone Unacceptable Performance Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions
Purpose of Todays Meeting
A public forum for discussion of the licensees A public forum for discussion of the licensees performance performance
NRC will address the licensee performance issues NRC will address the licensee performance issues identified in the annual assessment letter identified in the annual assessment letter
Licensee will respond to the information in the letter Licensee will respond to the information in the letter and inform the NRC of new or existing programs to and inform the NRC of new or existing programs to maintain or improve their performance 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
Performance Indicator Results (at end of CY 2003)
Green 1825 White 15 Yellow 0
Red 0
Total Inspection Findings (CY 2003)
Green 748 White 9
Yellow 2
Red 1
Braidwood Assessment Results (Jan 1 - Dec 31, 2003)
Unit 1: Regulatory Response Column
All Findings were categorized as very low safety significance (Green)
One Performance Indicator was within the White band
Unit 2: Licensee Response Column
All Findings were categorized as very low safety significance (Green)
All Performance Indicators were within the Green band
Mitigating System Unavailability Auxiliary Feedwater System - Unit 1
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
Supplemental Inspection 95001 will be conducted per the Action Matrix.
Braidwood Inspection Activities (Jan 1 - Dec 31, 2003)
(Jan 1 - Dec 31, 2003)
Completed Baseline Inspections - 2285hours
- Routine Integrated Inspections
- Triennial Fire Protection
- Engineering Plant Design
- Identification and Resolution of Problems
Unit 1 and Unit 2 Refueling Outages
Braidwood Inspection Activities (Jan 1 - Dec 31, 2004)
(Jan 1 - Dec 31, 2004)
Refueling Outage - Unit 1
Major team inspections
- Emergency Preparedness Exercise
Supplemental Inspection
- Auxiliary Feedwater System, Unit 1 - April 2004
Braidwood Annual Assessment Summary January 1 - December 31, 2003
Exelon operated Braidwood Units 1 & 2 in a manner that preserved public health and safety
All cornerstone objectives were met with only one White performance indicator in the Mitigating System Cornerstone
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
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)