ML051370585

Public Meeting Slides Braidwood End-of-Cycle Plant Performance Assessment

ML051370585
Person / Time
Site:	Braidwood
Issue date:	05/11/2005
From:	NRC/RGN-III
To:
References
Download: ML051370585 (20)

Text

Braidwood Annual Assessment Meeting Reactor Oversight Program - CY 2004 Nuclear Regulatory Commission - Region III Lisle, IL

Purpose of Todays Meeting

! A public forum for discussion of the licensees performance

! NRC will address Braidwood performance issues discussed in the March 2, 2005 annual assessment letter

! Licensee Remarks

Agenda

! Introduction

! Review of Reactor Oversight Process

! National Summary of Plant Performance

! Discussion of Plant Performance Results

! Licensee Remarks

! NRC Closing Remarks

! NRC available to address public questions

NRC Representatives

! Mark A. Satorius, Director, Division Reactor Projects

- (630) 829-9600

! Steven Reynolds, Deputy Division Director, DRP

- (630) 829-9600

! David Passehl, Branch Chief

- (630) 829-9872

! George Dick, Project Manager, NRR

- (315) 415-3019

! Nick Shah, Senior Resident Inspector

- (815) 458-2852

! Greg Roach, Resident Inspector

- (815) 458-2852

! Thomas Tongue, Senior Project Engineer

- (630) 829-9613

Region III Organization Regional Specialists Director Division of Reactor Safety Roy J. Caniano Deputy Director Cynthia D. Pederson Thomas Tongue Project Engineer Nick Shah Greg Roach Braidwood Resident Inspectors Branch Chief David Passehl Director Division of Reactor Projects Steve Reynolds Deputy Director Mark A. Satoriuis Regional Administrator Geoffrey Grant Deputy Regional Administrator Jim Caldwell

NRC Performance Goals

! Safety:Ensure protection of the public health and safety and the environment

! Security: Enhance the secure use and management of radioactive matrerials

! Openness: Ensure openness in our regulatory process

! Effectiveness: Ensure that NRC actions are effective, efficient, realistic, and timely

! Management: Ensure excellence in agency management to carry out the NRCs strategic objective

Reactor Oversight Process 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

! Emergency Preparedness

~80 hrs/yr

! Public Radiation Protection

~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 Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC Management Involvement with Licensee Management Increasing Regulatory Actions Licensee

Response

Regulatory

Response

Degraded Cornerstone Multiple/Rep.

Degraded Cornerstone Unacceptable Performance

National Summary of Plant Performance Status at End of CY 2004 Licensee Response 78 Regulatory Response 21 Degraded Cornerstone 0

Multiple/Repetitive Degraded Cornerstone 3

Unacceptable 0

• Davis-Besse is in IMC 0350 process Total Units 102

National Summary

! Performance Indicator Results (at end of CY 2004)

< Green 1834

< White 6

< Yellow 0

< Red 0

! Total Inspection Findings (CY 2004)

< Green 778

< White 11

< Yellow 0

< Red 0

Braidwood Assessment Results (Jan 1 - Dec 31, 2004)

! All Inspection Findings were Green

< Very Low Significance

! All Performance Indicators were within the Green band Licensee Response Column

Braidwood Inspection Activities (Jan 1 - Dec 31, 2004)

! Baseline Inspection

! Baseline Inspections were performed by the Resident Inspectors and Plant Support Staff.

! Supplemental 95001 Inspection

! Refueling Outage Inspections

! Other Inspections

Braidwood Inspection Activities (Jan 1 - Dec 31, 2004)

! Baseline Inspections were performed by Radiological Protection Inspectors and Security Inspectors

! An Emergency Preparedness Biennial Exercise Evaluation and Inspection was performed

! A Biennial Operator Licensing Requalification Inspection was performed

! An Inservice Inspection was performed Completed Baseline Inspections

Braidwood Inspection Activities (Jan 1 - Dec 31, 2004)

! 2515\\152 Reactor Pressure Vessel Lower Head Penetration Nozzles (Unit 1)

! 2515\\160 Pressurizer Penetration Nozzles and Steam Space Piping Connections (Unit1)

! 2515\\156 Offsite Power System Operational Readiness Other Inspections The Following Temporary Instructions (TI) were performed during 2004

Braidwood Annual Assessment Summary January 1-December 31, 2004

! Exelon operated Braidwood in a manner that preserved public health and safety

! All cornerstone objectives were met

! In 2005, NRC plans baseline inspections

Licensee 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)