ML071440468
| ML071440468 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 05/22/2007 |
| From: | NRC/RGN-III |
| To: | |
| References | |
| FOIA/PA-2010-0209 | |
| Download: ML071440468 (23) | |
Text
Braidwood Annual Assessment Meeting Braidwood Annual Assessment Meeting Reactor Oversight Program Reactor Oversight Program -- CY 2006 CY 2006 Nuclear Regulatory Commission Nuclear Regulatory Commission -- Region III Region III Braceville Braceville, IL
, IL May 22, 2007 May 22, 2007
Purpose of Todays Meeting zz Provide a Provide a public forum public forum for discussion of the for discussion of the licensees performance licensees performance zz NRC will address the licensee performance issues NRC will address the licensee performance issues identified in the identified in the annual assessment letter annual assessment letter zz Licensee Licensee will be given the will be given the opportunity to respond opportunity to respond to to the information in the letter and inform the NRC of the information in the letter and inform the NRC of new or existing programs to maintain or improve new or existing programs to maintain or improve their performance their performance
Agenda z Introduction z Review of Reactor Oversight Process z National Summary of Plant Performance z Discussion of Plant Performance Results z Licensee Response and Remarks z NRC Closing Remarks z Break z NRC available to address public questions
Region III Organization James Caldwell Regional Administrator Geoff Grant Deputy Regional Administrator Mark Satorius Director Division of Reactor Projects (DRP)
Steve West Deputy Director Cynthia Pederson Director Division of Reactor Safety (DRS)
Anne Boland Deputy Director Richard Skokowski Branch Chief Regional Specialists Braidwood Resident Inspectors Steven Ray Greg Roach Project Engineer Desiree Smith
NRC Representatives NRC Representatives z Steven Ray, Senior Resident Inspector (815) 458-2852 z Greg Roach, Resident Inspector (815) 458-2852 z Robert Kuntz, Project Manager, Nuclear Reactor Regulation (301) 415-3733 z Terry Brock, Health Effects Branch, Nuclear Regulatory Research (301) 415-2323 z Steven Orth, Health Physics Team Lead, DRS (630) 829-9827 z Viktoria Mitlyng, Public Affairs Officer, Region III (630) 829-9662 z John Cassidy, Health Physicist, DRS (630) 829-9667 z Richard Skokowski, Branch Chief, DRP (630) 829-9620
NRC Performance Goals z Safety: Ensure protection of the public health and safety and the environment z Security: Ensure the secure use and management of radioactive materials z Openness: Ensure openness in our regulatory process z Effectiveness: Ensure that NRC actions are effective, efficient, realistic, and timely z Management: Ensure excellence in agency management to carry out the NRCs strategic objectives
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
Significance Threshold Performance Indicators Green:
Baseline Inspection only 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
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
National Summary z Performance Indicator Results (at end of CY 2006)
Green 1843 White 11 Yellow 0
Red 0
z Total Inspection Findings (CY 2006)
Green 676 White 13 Yellow 0
Red 0
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 Radiological 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
Braidwood Assessment Results (Jan 1 - Dec 31, 2006) z Safety performance for Braidwood Units 1 and 2 for the most recent quarter was within the Regulatory Response column of the NRC Action Matrix.
z This assessment was based upon one inspection finding being classified as having low to moderate significance (White) in the public radiation safety cornerstone.
Significant Findings or PIs zz One significant finding, in public radiation safety, One significant finding, in public radiation safety, was identified during this assessment period. This was identified during this assessment period. This was associated with the licensees failure to perform was associated with the licensees failure to perform adequate, timely radiological evaluations following adequate, timely radiological evaluations following historical leaks.
historical leaks.
zz On February 2, 2007, the NRC completed a On February 2, 2007, the NRC completed a supplemental inspection pursuant to Inspection supplemental inspection pursuant to Inspection Procedure 95001 due to the White Performance Issue Procedure 95001 due to the White Performance Issue in the Public Radiation Safety cornerstone. No in the Public Radiation Safety cornerstone. No findings of significance were identified.
findings of significance were identified.
Public Radiation Safety Findings z November 2005 - Braidwood staff notified the NRC that tritium was detected in off-site wells.
z Braidwood investigation:
identified the source of tritium was from vacuum breaker valve leaks in 1996, 1998, and 2000 further identified a total of 17 occasions of vacuum breaker valve leaks.
characterized the release of radioactive material z Remediation Plan implemented after coordination with State of Illinois and NRC
Offsite Impact z Braidwood evaluated the potential dose to a member of the public from the releases, based on measurements from onsite and offsite wells and pathway evaluations Drinking water Bathing Cooking Watering gardens (vegetation)
Recreational usage of Exelon Pond and surrounding areas z Potential doses from the contamination were a very small fraction of the NRCs limits and relatively indistinguishable from fluctuations in normal background radiation dose.
NRC Evaluation Inspections encompassed activities from the initial response through evaluating Braidwoods root cause evaluation and corrective actions.
z Initial Response
Source of contamination and evaluation
Storage of water while repairing the discharge path z Review of remediation actions and resumption of liquid releases
Integrity of blowdown line
Integrity of modified vacuum breaker valve vaults including leak detection and alarm system z Independent dose calculation z Independent and duplicate analyses of water samples throughout the inspection period z External communications Results -- One WHITE finding and violations of NRC requirements
Braidwood Inspection Activities (Jan 1 (Jan 1 -- Dec 31, 2006)
Dec 31, 2006) z 10 findings during this assessment period 2 in initiating events 3 in mitigating systems 2 in barrier integrity 3 in public radiation safety
Braidwood Inspection Activities (Jan 1 - Dec 31, 2006) z Supplemental Inspection 95001 was completed on February 2, 2007 z Unit 1 had a refueling outage from April 16 - May 3, 2006. During this outage the licensee identified a pressurizer heater housing crack which was caused by intergranular stress corrosion cracking, the first case ever identified.
z Unit 2 had a refueling outage from October 15 -
November 2, 2006
Braidwood Annual Assessment Summary (Jan 1 - Dec 31, 2006) z Exelon Nuclear operated Braidwood Units 1 & 2 in a manner that preserved public health and safety z All cornerstone objectives were met with only one White Finding identified for the Public Radiation Safety Cornerstone.
z NRC plans baseline inspections at Braidwood for the remainder of the assessment period. A supplemental 95001 inspection was completed on February 2, 2007.
Licensee Response and Remarks Tom Coutu Site Vice President Braidwood Generating Station
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 About NRC > Organization and Functions 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) z Illinois EPA Environmental Emergencies Only 1-800-782-7860 (24 hrs/day, Toll Free) 217-782-7860 (24 hrs/day)