ML051080310

NRC CY2004 - Annual Assessment Meeting. Sequoyah Nuclear Plant

ML051080310
Person / Time
Site:	Sequoyah
Issue date:	04/12/2005
From:	NRC/RGN-II
To:
References
Download: ML051080310 (18)

Text

NRC CY2004 Annual Assessment Meeting Sequoyah Nuclear Plant Soddy Daisy, TN April 12, 2005

Purpose of Todays Meeting

• A public forum for discussion of Sequoyah performance

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

• Sequoyah 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 Sequoyah Plant Performance Results

• Sequoyah Management Response and Remarks

• NRC Closing Remarks

• Break

• NRC Available to Address Public Questions

Region II Organization 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 Sequoyah Project Engineers Resident Inspectors Scott Shaeffer Scott Freeman Robert Carrion Mark Speck 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

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 Total 102*

• Davis-Besse is under a special inspection process

Sequoyah CY2004 Inspection Activities 3600 hours0.0417 days <br />1 hours <br />0.00595 weeks <br />0.00137 months <br /> of inspection related activities, including:

• Licensed operator requalification inspection

• Radiation protection inspections

• Maintenance inspection

• ISFSI pre-operational inspections

• Emergency preparedness inspections

• Reactor operator initial exam

• Unit 1 outage-related in-service inspections

Sequoyah Unit 1 CY2004 Assessment Results

• Unit 1 performance was within the Licensee Response Column of the NRCs Action Matrix for the first two quarters of 2004.

• Unit 1 performance was within the Regulatory Response Column of the NRCs Action Matrix for the last two quarters of 2004 based on one inspection finding of low-to-moderate increased importance to safety (White).

- The finding was associated with the Mitigating Systems Cornerstone and involved a failure of a residual heat removal pump to start during surveillance testing in July 2004, when the pump breaker failed to close.

• All Unit 1 performance indicators were Green

Sequoyah Unit 2 CY2004 Assessment Results

• Unit 2 performance was within the Licensee Response Column of the NRCs Action Matrix.

• All Unit 2 inspection findings were classified as very low safety significance (Green).

• All Unit 2 performance indicators were Green

Sequoyah Annual Assessment Outcome Summary

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

• All cornerstone objectives were met

• NRC planned baseline inspections at Sequoyah for the remainder of CY 2005 as well as:

- Supplemental Inspection of TVAs root cause evaluation on the White finding (completed satisfactorily in March 2005)

- Routine ISFSI inspections for Sequoyah

Sequoyah CY2005 Planned Inspection Activities

• Resident inspector daily inspections

• Radiation protection inspections

• Emergency preparedness inspections

• Problem identification and resolution inspection

• Engineering modification inspection

• Safety system design and performance inspection

• Fire protection inspection

• ISFSI operations inspection

• Unit 2 outage-related inservice inspections

• Supplemental inspection for one White finding in a strategic performance area (95001)

NRC CY2004 Annual Assessment Meeting Sequoyah 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)