ML071990357

EOC Meeting Slides

ML071990357
Person / Time
Site:	McGuire, Mcguire
Issue date:	04/30/2007
From:	NRC/RGN-II
To:
Shared Package
ML071990350	List: ML071990355 ML071990357
References
Download: ML071990357 (21)

Text

NRC CY2006 Annual Assessment Meeting McGuire Nuclear Station Huntersville, NC April 30, 2007

Purpose of Todays Meeting

• Provide a public forum for discussion of McGuire performance

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

• McGuire 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

• National Summary of Plant Performance

• Discussion of McGuire Plant Performance Results

• McGuire Management Response and Remarks

• NRC Closing Remarks

• Break

• NRC Available to Address Public Questions

Region II Organization William Travers Regional Administrator Victor McCree Deputy Regional Administrator Charles Casto Joseph Shea Director Division of Reactor Projects Director Division of Reactor Safety Harold Christensen Kriss Kennedy Deputy Director Deputy Director Jim Moorman Regional Specialists Branch Chief McGuire Nuclear Station Project Engineer Joe Brady, SRI Curt Rapp, SPE Shakur Walker, RI

NRC Performance Goals PRIMARY GOALS Ensure protection of the public health and safety and the environment Ensure 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 The NRC monitors plant performance in three major areas:

Reactor Safety (avoiding accidents or transient &

reducing their consequences if they occur)

Radiation Safety (both plant workers & the public during routine operations)

Security (protection of the plant against sabotage or other security threats) . . . . . Major changes in the post-9/11 environment

Reactor Oversight Process Reactor Oversight Process The ROP includes two separate sources of information:

• Inspections conducted by NRC personnel

• Performance Indicators developed from data provided by licensees Inspectors can be Site-based or Region-based Together they provide a composite picture of how the plant is being operated

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 Rad 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

CORNERSTONE PERFORMANCE INDICATORS Initiating Events - Unplanned Scrams

- Scrams with Loss of Normal Heat Sink

- Unplanned Power Changes Mitigating Systems - Safety System Functional Failure

- Mitigating Systems Performance Indicators Barrier Integrity - Reactor Coolant Activity

- Reactor Coolant System Leakage Emergency Preparedness - Drill/Exercise Performance

- ERO Drill Participation

- Alert and Notification System Occupational Radiation Safety - Occupational Exposure Control Public Radiation Safety - RETS/ODCM Radiological Effluent Safeguards - Physical Protection (not publicly available)

Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Baseline Inspection Performance Indicator Results Results Significance Significance Threshold Threshold Action Matrix NRC Response

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 Interaction and 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

McGuire CY2006 Inspection Activities

• ~2200 hours of inspection related activities

• Resident inspector daily inspections

• Triennial Fire Protection Inspection

• Radiation Protection Inspections

• In-service Inspection (U2)

• Reactor Pressure Vessel &Vessel Head Penetration Nozzles (U2)

• Mitigating Systems Performance Indicator Initial Verification

• Component Design Basis Verification

• Licensed Operator Requalification Inspection

• Emergency Preparedness Inspection

• Independent Spent Fuel Storage Facility

McGuire CY2006 Assessment Results

• Plant performance was within the Licensee Response Column of the NRCs Action Matrix

• All inspection findings were classified as being of very-low safety significance (Green)

• All Performance Indicators (PI) were Green

McGuire CY2006 Assessment Summary

• Duke Power Company, LLC operated McGuire in a manner that preserved public health and safety

• All cornerstone objectives were met

• NRC plans to conduct baseline inspections at McGuire for the remainder of CY 2007.

McGuire CY2007 Scheduled Inspection Activities

• Resident Inspector Daily Inspections

• Biennial Problem identification and Resolution

• Modification (10CFR50.59) Inspections

• Heat Sink Performance

• Emergency Preparedness Exercise

• Reactor Pressure Vessel & Vessel Head Penetration Nozzles (U1)

• Radiation Protection Baseline Inspection

• Heat Sink Performance

• In-service Inspection (U1)

• Containment Sump Blockage TI (U1)

• Maintenance Effectiveness

• Reactor Operator Licensing Examinations

NRC CY2006 Annual Assessment Meeting McGuire Nuclear Station McGuire Station Management Response & 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 Public Web Site: 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)