MN 06-004, NRC Slides for Public Meeting with Entergy Nuclear Northeast (Indian Point 2 & 3) to Discuss Cy 2005 Annual Assessment

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NRC Slides for Public Meeting with Entergy Nuclear Northeast (Indian Point 2 & 3) to Discuss Cy 2005 Annual Assessment
ML060830370
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 03/24/2006
From: Brian Mcdermott
Reactor Projects Branch 2
To:
McDermott, B J, RGN-I/DRP/610-337-5233
Shared Package
ML060660402 List:
References
MN 06-004
Download: ML060830370 (27)


Text

NRC Annual Assessment Meeting For Indian Point Peekskill, New York March 28, 2006 Nuclear Regulatory Commission - Region I

2 Purpose of Todays Meeting

  • A public forum for discussion of the licensees performance
  • The NRC will present its assessment of safety performance at Indian Point during 2005
  • Entergy will be given the opportunity to respond and describe new or existing programs to maintain or improve its performance

3 Agenda

  • Introduction
  • Review of Reactor Oversight Process
  • National Summary of Plant Performance
  • Discussion of Plant Performance Results
  • Licensee Response and Remarks
  • NRC Closing Remarks
  • Break
  • NRC available to address public questions

4 Region I Organization NRC Region I Samuel J. Collins, Regional Administrator Marc L. Dapas, Deputy Regional Administrator Director Division of Reactor Projects Brian E. Holian, Director David C. Lew, Deputy Director Director Division of Reactor Safety A. Randolph Blough, Director Marsha K. Gamberoni, Deputy Director Projects Branch 2 Eugene W. Cobey, Chief Regional Specialist Branches Indian Point Resident Inspectors Mark R. Cox Thomas R. Hipschman Gregory T. Bowman Brian D. Wittick Project Engineers Donald E. Jackson Christopher M. Long Stacy M. Smith Ayo Ayegbusi

5 NRC Representatives Samuel Collins, Regional Administrator, Region I Brian McDermott, Chief, Projects Branch 1, Region I Gene Cobey, Chief, Projects Branch 2, Region I Mark Cox, Senior Resident Inspector IP2 Tom Hipschman, Senior Resident Inspector IP3 Diane Screnci, Senior Public Affairs Officer, Region I Patricia Milligan, Senior Advisor on Emergency Preparedness, Office of Nuclear Security and Incident

Response

John Boska, Project Manager, Office of Nuclear Reactor Regulation

6 NRC Performance Goals

  • Safety: Ensure protection of the public health and safety and the environment
  • Security: Ensure the secure use and management of radioactive materials
  • Openness: Ensure openness in our regulatory process
  • Effectiveness: Ensure that NRC actions are effective, efficient, realistic, and timely
  • Management: Ensure excellence in agency management to carry out the NRCs strategic objectives

7 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

8 Examples of Baseline Inspections 1

  • Equipment Alignment

~80 hrs/yr

  • Triennial Fire Protection

~200 hrs/3 yrs

  • Operator Response

~125 hrs/yr

~80 hrs/yr

  • Rad Release Controls

~110 hrs/2 yrs

  • Engineering Design

~680 hrs/2 yrs

  • Corrective Action Program

~250 hrs/2 yrs

  • Corrective Action Case Reviews ~60 hrs/yr 1Baseline Inspections For A Single Unit Require Approximately ~5000 Hours Per Year

9 Significance Threshold Inspection Findings Green:

Very low safety significance White:

Low to moderate safety significance Yellow:

Substantial safety significance Red:

High safety significance Performance Indicators Green:

Baseline Inspection White:

Increased NRC oversight Yellow:

Requires more NRC oversight Red:

Requires more NRC oversight

10 Action Matrix Concept

  • Increasing Safety Significance
  • Increasing NRC Inspection Efforts
  • Increasing NRC/Licensee Management Involvement
  • Increasing Regulatory Actions ResponseResponse CornerstoneDegraded CornerstonePerformance Licensee

Response

Regulatory

Response

Degraded Cornerstone Multiple/Rep.

Degraded Cornerstone Unacceptable Performance

11 National Summary Status At End Of 2005 2004 Licensee Response 84 78 Regulatory Response 12 21 Degraded Cornerstone 4

0 Multiple/Repetitive Degraded Cornerstone 3

3 Unacceptable 0

0 Total 103 102*

  • Davis-Besse was in Shutdown with Enhanced Oversight in 2004

12 National Summary Performance Indicator Results Status At End Of 2005 2004 Green 1850 1834 White 4

6 Yellow 0

0 Red 0

0 Total Inspection Findings Total For Calendar Year 2005 2004 Green 849 778 White 10 11 Yellow 1

0 Red 0

0

13 NRC Inspection Findings Available On The Web At: http://www.nrc.gov/reactors/operating/oversight.html

14 NRC Performance Indicators Available On The Web At: http://www.nrc.gov/reactors/operating/oversight.html

15 Indian Point 2 Performance

  • Regulatory Response Column Of NRC Reactor Oversight Process Action Matrix

- One White Finding (Second Quarter 2005)

- Supplemental Inspection (December 2005)

- All Performance Indicators Green

- Return To Licensee Response Column In 2nd Quarter 2006 Based On Current Performance

  • Closed Substantive Cross-Cutting Issue For Problem Identification And Resolution January 1, 2005 - December 31, 2005

16 Cross-Cutting Issue Closed

  • Problem Identification And Resolution Issue Opened in 2001 NRC Annual Assessment

- Untimely And Ineffective Corrective Actions

  • NRC Semi Annual Review Of Findings

- Improvements Noted But Inconsistent Implementation 2005 Mid Cycle Review

- Improved Performance On Corrective Action

- Focus Shifted To Problem Evaluation

  • 2005 End Of Cycle Review

- Problem Evaluation Performance Improved

17 Indian Point 2 Timeline 2000 2001 2002 2003 2004 Electrical Distribution Finding Steam Generator Tube Leak Finding Operator Training Finding Degraded Fire Barrier Finding 2005 Nitrogen Gas Accumulation Finding Degraded Cornerstone Multiple Degraded Cornerstone Degraded Cornerstone Regulatory

Response

Licensee Response Regulatory

Response

NRC Action Matrix And Oversight ROP Deviation Memorandum

18 Indian Point 2 Inspections

  • 6917 Hours of Inspection Related Activities
  • Four Full-time Resident Inspectors (IP2 and IP3)
  • Eight Regional Specialist Inspection Activities
  • Three NRC Team Inspections

- Safety System Design

- Problem Identification and Resolution

- Special Inspection for Spent Fuel Pool/Tritium

  • Supplemental And ROP Deviation Inspections January 1, 2005 - December 31, 2005

19 Indian Point 3 Performance

  • Licensee Response Column of NRC Reactor Oversight Process Action Matrix

- All Inspection Findings Green

- All Performance Indicators Green January 1, 2005 - December 31, 2005

20 Indian Point 3 Inspections

  • 5292 Hours of Inspection Related Activities
  • Four Full-time Resident Inspectors (IP2 and IP3)
  • Ten Regional Specialist Inspection Activities
  • Two NRC Team Inspections

- Triennial Fire Protection

- Safety System Design January 1, 2005 - December 31, 2005

21 Upcoming NRC Activities

  • NRC Inspection Teams

- Problem Identification and Resolution

- Plant Modifications

- Emergency Preparedness Exercise

  • Preparations for Design Bases Inspection Teams
  • ROP Deviation Inspection And Oversight

- Siren System Corrective Actions And Upgrades

- Groundwater Contamination Investigation Significant Activities In 2006 At Indian Point 2 and 3

22 Licensee Response and Remarks

23 Summary Of NRC Assessment

  • Entergy Operated Indian Point In A Manner That Preserved Public Health and Safety During 2005
  • NRC Closed A Long-Standing Issue Concerning Problem Identification And Resolution Based On Entergys Progress And Performance
  • NRC Will Conduct Baseline Inspections At Indian Point During 2006
  • Additional NRC Oversight Will Be Applied To Assess Entergys Progress On Tritium Contamination and Siren Issues

24 ROP Deviation

  • Enhanced Inspection For Two Issues Approved By NRC Senior Management In October 2005

- Spent Fuel Pool Leakage and Contamination

- Alert and Notification System (Sirens) Corrective Actions and Backup Power Upgrades

  • Separate NRC Public Meeting To Discuss The Groundwater Contamination Issue

25 Contacting the NRC

  • To report an emergency (301) 816-5100 (call collect)
  • To report a safety concern (800) 695-7403 or Allegation@nrc.gov General information or questions www.nrc.gov Select What We Do for Public Affairs

26 Reference Sources Reactor Oversight Process http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html Public Electronic Reading Room http://www.nrc.gov/reading-rm.html Public Document Room 1-800-397-4209 (Toll Free)

27 Public Question and Answer

  • Please sign up to ask questions during the public Q&A session

- Time for questions from one individual or organization may be limited to ensure other members of the public have the opportunity to ask questions

  • We will have a 10 minute break before the public Q&A session - during this time, please feel free to ask questions of the individual NRC staff