ML072050220

Public Meeting Slides for Catawba

ML072050220
Person / Time
Site:	Catawba
Issue date:	05/03/2007
From:	Division Reactor Projects II
To:
Shared Package
ML072050158	List: ML072050160 ML072050220
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Download: ML072050220 (22)

Text

NRC CY2006 Annual Assessment Meeting Catawba Nuclear Station Rock Hill, SC May 3, 2007

Purpose of Todays Meeting

• Provide a public forum for discussion of Catawba performance

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

• Catawba 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 Catawba Plant Performance Results

• Catawba 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 Catawba Nuclear Station Project Engineer Andrew Sabisch; SRI Curt Rapp, SPE Gordon Williams, RI Lee Harmon, OA

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

- Emergency AC Power System

- High Pressure Injection System

- Heat Removal System

- Residual Heat Removal System

- Cooling Water Systems Barrier Integrity - Reactor Coolant Activity

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

- ERO Drill Participation

- Alert and Notification System Occupational Radiation - Occupational Exposure Control Safety 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 Nuclear 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

Catawba CY2006 NRC Inspection Activities

• ~2400 hours of direct inspection-related activities

• Resident inspector daily inspections

• Additional baseline inspections conducted by Regional inspectors

• Resident inspector changes

• Andy Sabisch promoted to SRI in 9/06

• Gordon Williams assigned as RI in 11/06

Catawba CY2006 Inspection Activities Conducted Problem Identification & Resolution Inspection Independent Spent Fuel Storage Facility Emergency Preparedness R.P. Baseline Inspection Modifications Inspection In-service Inspection (U1 & U2)

Steam Generator ISI (U1 & U2)

Reactor Vessel Head Inspection (U1)

Reactor Operator Initial License Examination Reactor Operator Requalification Inspection

Catawba 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

Catawba CY2006 Assessment Summary

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

• All cornerstone objectives were met

• NRC plans to conduct baseline inspections at Catawba for the remainder of CY 2007 with some routine supplemental inspections

Catawba CY2007 Scheduled Inspection Activities Security Force-on-Force Performance Component Design Basis Inspection ISFSI Dry Run & Initial Cask Loads Emergency Preparedness Triennial Fire Protection Inspection R.P. Baseline Inspection Heat Sink Performance Inservice Inspection (U2)

Containment Sump Modifications (U2)

Steam Generator ISI (U2)

Reactor Vessel Head Inspection (U2)

Reactor Operator Licensing Examinations

NRC CY2006 Annual Assessment Meeting Catawba Nuclear Station Catawba 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/in dex.html z Public Electronic Reading Room http://www.nrc.gov/reading-rm.html z Public Document Room 1-800-397-4209 (Toll Free)