ML051100154

Slides for NRC CY2004 Annual Assessment Meeting, Watts Bar

ML051100154
Person / Time
Site:	Watts Bar
Issue date:	04/18/2005
From:	NRC/RGN-II
To:
References
Download: ML051100154 (18)

Text

Annual Assessment Meeting Watts Bar Nuclear Plant Spring City, TN April 18, 2005

Purpose of Todays Meeting

• A public forum for discussion of Watts Bar performance

• NRC will address Watts Bar performance issues identified in the annual assessment letter

• Watts Bar 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 (ROP)

• National Summary of Plant Performance

• Discussion of Watts Bar Plant Performance Results

• Watts Bar Management Response and Remarks

• NRC Closing Remarks

• Break

• NRC Available to Address Public Questions

William Travers Regional Administrator Loren Plisco Deputy Regional Administrator Victor McCree Charles Casto Director Division of Reactor Projects Director Division of Reactor Safety Leonard Wert Harold Christensen Deputy Director Deputy Director Stephen Cahill Branch Chief Watts Bar Project Engineers Resident Inspectors Scott Shaeffer Jonathan Bartley Robert Carrion James Reece Michael Pribish

NRC Performance Goals PRIMARY GOALS Ensure protection of the public health and safety and the environment Enhance 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

• Equipment Alignment ~92 hrs/yr

• Triennial Fire Protection ~200 hrs every 3 yrs

• Operator Response ~125 hrs/yr

• Emergency Preparedness ~80 hrs/yr

• Rad Release Controls ~100 hrs every 2 yrs

• Worker Radiation Protection ~100 hrs/yr

• Corrective Action Program ~250 hrs every 2 yrs

• 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

Plant Performance Status at End of CY 2004 Licensee Response 78 Regulatory Response 21 Degraded Cornerstone 0 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total 102*

• Davis-Besse is under a special inspection process

Inspection Activities Approx. 4100 hours0.0475 days <br />1.139 hours <br />0.00678 weeks <br />0.00156 months <br /> of inspection related activities, including:

• Licensed operator requalification inspection

• Radiation protection inspections

• Maintenance inspection

• Triennial Fire protection inspection

• Emergency preparedness inspections

• Reactor operator initial exam

• Unit 2 Systems layup inspection

Watts Bar CY2004 Assessment Results At the time the Assessment Letter was issued on March 2, 2005:

• All performance indicators were Green

• All Unit 1 inspection findings for CY 2004 were classified as very low safety significance (Green)

• Unit 1 performance was considered within the Licensee Response Column of the NRCs Action Matrix

Watts Bar CY2004 Assessment Results We subsequently issued a final significance determination letter and notice of violation on April 11, 2005:

• Issue involving silt clogging of a back-up raw cooling water line to the 1A Charging Pump discovered by TVA in November 2004

• We identified an inspection finding for inadequate corrective action on previous silt problems that did not prevent this clog

• Finding was unresolved while the NRC determined safety significance and allowed TVA to supply additional information. Issue was determined to be a White Finding (issue with low to moderate safety significance).

• Unit 1 performance now considered within the Regulatory Response Column of the NRCs Action Matrix effective from the 4th Quarter of CY 2004

Assessment Outcome Summary

• TVA operated Watts Bar in a manner that preserved public health and safety

• All cornerstone objectives were met

• NRC had planned baseline inspections at Watts Bar for the remainder of CY 2005 as well as:

- Routine Unit 2 Lay-up inspections

- Steam generator replacement preparation inspections

• We will now also perform a Supplemental Inspection of TVAs root cause evaluation on the White finding (schedule is being planned)

Planned Inspection Activities

• Resident inspector daily inspections

• Radiation protection inspections

• Maintenance inspection

• Emergency preparedness inspections

• Problem identification and resolution inspection

• Engineering modification inspection

• Safety system design and performance inspection

• Supplemental Inspection for the White Finding

Annual Assessment Meeting Watts Bar Management Response and Remarks

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)