ML111672121

Annual Assessment Meeting Slides

ML111672121
Person / Time
Site:	Indian Point
Issue date:	06/16/2011
From:	Mel Gray Reactor Projects Branch 2
To:
Gray, Mel NRC/RGNI/DRP/PB2/610-337-5209
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ML110610687	List: IR 05000247/2010001 ML111220200 ML111672121
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Download: ML111672121 (27)

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Indian Point 2 & 3 Annual Assessment Meeting Slides June 16, 2011 ML111672121 1

Indian Point 2 & 3 Assessment Meeting Indian Point 2 & 3 Safety Performance in 2010 U.S. Nuclear Plant Safety in light of Events in Japan Nuclear Regulatory Commission - Region I June 2, 2011 2

Agenda

• Introduction

• Discussion of Indian Point 2/3 safety performance

• Discussion of U.S. nuclear plant safety in light of events in Japan

• NRC to address public questions

• Closing remarks 3

• Entergy operated Indian Point 2 & 3 safely and in a manner that preserved the public health and safety and protected the environment

• Licensee Response column of the Action Matrix for each unit

• Baseline inspections planned for each unit in 2011 NRC Assessment Summary 4

• 6460 hours0.0748 days <br />1.794 hours <br />0.0107 weeks <br />0.00246 months <br /> of inspection and related activities

• 2 resident inspectors on site - residents perform inspections daily and can respond to plant events at any time

• 11 regional inspections

• 4 major team inspections Triennial Fire Protection Initial Operator Licensing Exam Problem Identification and Resolution Emergency Procedures Exercise Indian Point 2 Inspection Activities in 2010 5

• All Green Performance Indicators

• 17 Green/Severity Level IV inspection findings

• No greater than Green inspection findings January 1 through December 31, 2010 Indian Point 2 Performance Indicator and Inspection Results 6

• 4980 hours0.0576 days <br />1.383 hours <br />0.00823 weeks <br />0.00189 months <br /> of inspection and related activities

• 2 resident inspectors on site - residents perform inspections daily and can respond to plant events at any time

• 13 regional inspections

• 3 major team inspections Initial Operator Licensing Exam Emergency Procedure Exercise Component Design Bases Indian Point 3 Inspection Activities in 2010 7

• One White Performance indicator in Initiating Events (1st Qtr)

• All other Performance Indicators Green

• 10 Green inspection findings

• No greater than Green inspection findings January 1 through December 31, 2010 Indian Point 3 Performance Indicator and Inspection Results 8

Indian Point 2 & 3 NRC Action Matrix Increasing safety significance Increasing NRC inspection efforts Increasing NRC/Licensee management involvement Increasing regulatory actions Licensee

Response

Regulatory

Response

Degraded Cornerstone Multiple Repetitive Degraded Cornerstone Unacceptable Performance All Inputs are Green; Cornerstone Objectives Fully Met 1 or 2 White Inputs; Cornerstone Objectives Fully Met 2 White or 1 Yellow Input; Cornerstone Objectives Met w/

Moderate Degradation in Safety Performance Multiple Yellow Inputs or 1 Red Input; Cornerstone Objectives Met w/

Significant Degradation in Safety Performance Overall Unacceptable Performance; Plants not permitted to Operate w/in this Column; Unacceptable Margin to Safety

• Indian Point 2 & 3 operated safely

• Licensee Response column of the Action Matrix

• Baseline inspections planned for 2011 2010 Indian Point 2 & 3 Assessment Summary 10

Indian Point 2 & 3 Assessment Meeting U.S. Nuclear Plant Safety in Light of Events in Japan 11

Fukushima: Facts We Know Today

• 9.0 Earthquake

- 4th largest in the world since 1900

• Reactors safely shutdown

• Site then hit by a ~40 foot Tsunami

• Tsunami caused a loss of all electrical power 12

Fukushima: Facts We Know Today

• Loss of all electrical power to safety systems eventually led to fuel damage

• Secondary containment hydrogen explosions visible at Units 1 & 3 several days later

• Radiological releases 13

U.S. Considerations

• No anticipated U.S. health effects from Fukushima

• Methodical and systematic review in progress

• U.S. nuclear plants remain safe

- NRC requires plants to be designed to withstand external events

- NRC requires a defense-in-depth approach

- NRC performs independent safety inspections

- NRC assesses new safety information and requires improvements.

14

U. S. Plants Designed for Site Specific Natural Events

• Earthquakes

• Tsunamis

• Hurricanes

• Floods

• Tornadoes 15

Indian Point Seismic Considerations

• NRC seismic designs based on ground shaking

• Plants designed to a ground-shaking level appropriate for location

• Design basis considered largest observed earthquake in region in historical times

• Design includes seismic safety margins

• Ramapo fault system taken into account 16

The NRC Requires Defense-In-Depth

• Redundant and diverse safety systems

• Multiple physical barriers to contain radioactive material

• Testing and inspection of systems important to safety

• Emergency planning 17

NRC Independent Safety Inspections Reactor Oversight Program

• NRC inspectors have unfettered access to all plant activities related to nuclear safety and security

• At least two full-time NRC resident inspectors at each nuclear plant

• NRC specialists conduct additional inspections at each nuclear plant 18

NRC Requires Safety Improvements NRC assesses new safety information, develops lessons learned, and requires safety enhancements:

19

• NRC operating experience program

• Rulemaking (Station Blackout)

• Post TMI Actions

• Post 9/11 Orders

• Generic Safety Issues

NRC Response to Events in Japan

• NRC response & assistance to Japanese government

• NRC conducting a methodical and systematic review 20

• Near-term actions (~90 days)

- conducted additional inspections

- identifying near term operational issues

• Longer-term actions

NRC Near-Term Review

• Evaluate Fukushima Daiichi Events

• Domestic operating reactors and spent fuel pools

• Staff briefed the Commission in a public meeting on May 12

• Next briefing scheduled for June 16

• Final recommendations in public meeting July 19 21

NRC Long-Term Review

• Sequence of events and the status of equipment during the event

• Evaluate all technical and policy issues

• Evaluate potential interagency issues

• Applicability of lessons learned to non-operating reactor and non-reactor facilities

• Report to the Commission within 6 months from the start of the evaluation 22

Emergency Planning Zones and Protective Action Recommendations

• Limited and uncertain data was available

• Significant challenges to 3 units and at least 2 spent fuel pools on site

• Potential for large offsite release existed

• Elevated dose rates on site presented challenges to crews attempting to stabilize reactor

• Limited offsite data suggested serious damage to fuel

• Winds shifting from out to sea to land 23

NRC Actions to Date

• Information Notice 2011-05, Tohoku-Taiheiyou-Oki Earthquake Effects on Japanese Nuclear Power Plants

• Emergent NRC Inspections in Response to Fukushima Events

• Bulletin 2011-01, Mitigating Strategies

• Task force established 24

Summary

• Safety of current facilities remains top priority

• The NRC will continue to perform a systematic and methodical review of the Fukushima event

• The NRC will take action based on results of the review to ensure the continued safety of U.S. commercial nuclear power plants 25

Meeting Ground Rules

1. Please be respectful to the speaker - only one speaker at a time

2. See NRC staff if you have procedural questions/concerns or still want to sign up.

3. NRC staff members will be available after the meeting to talk to those interested 26

Questions 27