ML080880083

Slides - NRC & Neac Meeting Concerning Millstone Station Performance, 2007 Reactor Oversight Program

ML080880083
Person / Time
Site:	Millstone
Issue date:	03/28/2008
From:	Norris B NRC/RGN-I/DRP/PB5
To:
Powell R, RI/DRP/610-337-6967
References
Download: ML080880083 (22)

Text

NRC & NEAC Meeting Concerning Millstone Station Performance 2007 Reactor Oversight Program

Purpose of Todays Meeting

• A public forum for discussion of Millstones Plant Performance for CY 2007

• NRC will address Millstones performance as discussed in the NRC Annual Assessment Letter to Dominion Nuclear Connecticut, Inc.

• NEAC will be given the opportunity to respond to the information, request clarifications, and ask additional questions, as needed 2

Agenda

• Introduction

• Review of Reactor Oversight Process (ROP)

• National Summary of Plant Performance

• Millstones Performance Results

• NEAC Response and Remarks

• NRC & NEAC Closing Remarks

• Break

• NRC available to address questions/comments 3

Region I Organization Samuel J. Collins Regional Administrator Marc L. Dapas Deputy Regional Administrator David C. Lew Marsha K. Gamberoni Director Division of Reactor Projects Director Division of Reactor Safety James W. Clifford Darrell J. Roberts Deputy Director Deputy Director Raymond J. Powell Regional Specialists Branch Chief Millstone Resident Inspectors Project Engineers Steve W. Shaffer - Senior RI Barry S. Norris - Senior PE Jamie C. Benjamin - RI Nicole S. Sieller - PE James A. Krafty - RI 4

NRC Strategic Plan Goals 3/4 Safety: Ensure adequate protection of public health and safety and the environment 3/4 Security: Ensure adequate protection in the secure use and management of radioactive materials 5

Reactor Oversight Process 3 Strategic Areas & 7 Cornerstones Reactor Radiation Safeguards Safety Safety Public Occupational Initiating Mitigating Barrier Emergency Physical Radiation Radiation Events Systems Integrity Preparedness Protection Safety Safety 6

Reactor Oversight Process S tra te g ic P e rfo r m a n c e A re a s S a fety C o rn e r s to n e s B a s e lin e In s p e c tio n P e r fo r m a n c e In d ic a to r R e s u lts R e s u lts S ig n ific a n c e S ig n ific a n c e T h r e s h o ld T h r e s h o ld A c tio n M a tr ix R e g u la to ry R e s p o n s e 7

Typical Baseline Inspection Areas

• Equipment Alignment

• Maintenance

• Fire Protection

• Operator Response

• Emergency Preparedness

• Radiological Environmental Monitoring

• Worker Radiation Protection

• Corrective Action Program

• Corrective Action Case Reviews 8

NRC Performance Indicators Initiating Events PIs

• Unplanned Scrams

• Unplanned Scrams with Complications

• Unplanned Power Changes Mitigating Systems PIs

• Emergency AC Power System

• High Pressure Injection System

• Residual Heat Removal System

• Cooling Water Support Systems

• Safety System Functional Failures Barrier Integrity PIs

• Reactor Coolant System Specific Activity

• Reactor Coolant System Leakage Emergency Planning PIs

• Drill / Exercise Performance

• Emergency Response Organization Participation

• Alert and Notification System Radiation Protection PIs

• Occupational Exposure Control Effectiveness

• RETS / ODCM Radiological Effluent Security PIs are not Publicly Available 9

Significance Threshold Performance Indicators 3/4 Green Baseline Inspection 3/4 White Requires increased NRC oversight 3/4 Yellow Requires more NRC oversight 3/4 Red Requires most NRC oversight Inspection Findings 3/4 Green Very low safety issue 3/4 White Low to moderate safety issue 3/4 Yellow Substantial safety issue 3/4 Red High safety issue 10

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 11

National Summary of Plant Performance (at end of 2007)

Licensee Response 87 Regulatory Response 8 Degraded Cornerstone 8 Multiple/Repetitive Degraded Cornerstone 1 Unacceptable 0 Total 104 12

National Summary of Plant Performance (at end of 2007)

Performance Indicator Results 3/4 Green 1954 3/4 White 8 3/4 Yellow 2 3/4 Red 0 Total Inspection Findings 3/4 Green 918 3/4 White 9 3/4 Yellow 2 3/4 Red 0 13

Millstone Assessment Summary (CY 2007)

• Licensee Response Column

• No safety significant Findings or Performance Indicators

- All Green Performance Indicators

- 14 Green inspection findings 14

NRC Inspection Activities (January 1 - December 2007)

• Inspection and related activities

- 2703 hours0.0313 days <br />0.751 hours <br />0.00447 weeks <br />0.00103 months <br /> at Millstone Unit 2

- 3977 hours0.046 days <br />1.105 hours <br />0.00658 weeks <br />0.00151 months <br /> at Millstone Unit 3

• 3 resident inspectors assigned to site

• Inspections

- Units 2 & 3 - 3 team & 10 regional inspections

- Unit 2 only - 2 regional inspection

- Unit 3 only - 1 team & 5 regional inspections 15

NRC Inspection Activities (January 1 - December 2007)

• Inspection Findings

- 4 findings of very low safety significance (Green) at Unit 2

- 9 findings of very low safety significance (Green) at Unit 3

- 1 finding of very low safety significance (Green) common to both units

• Unit 3 refueling outage (April 6 - May 18)

- 2 findings of very low safety significance (Green) 16

NRC Annual Assessment Summary

• Dominion operated Millstone safely and in a manner that preserved public health and safety and protected the environment

• All cornerstone objectives were fully met

• NRC plans baseline inspections at Millstone for the remainder of CY 2008 17

NRC Representatives

• James W. Clifford, Deputy Division Director, DRP 3/4 610-337-5080

• Raymond J. Powell, Branch Chief 3/4 610-337-6967

• Steve W. Shaffer, Senior Resident Inspector 3/4 860-447-3170

• Jamie C. Benjamin, Resident Inspector 3/4 860-447-3170

• James A. Krafty, Resident Inspector 3/4 860-447-3170

• Barry S. Norris, Senior Project Engineer 3/4 610-337-5111 18

Contacting the NRC

• Report an emergency:

3/4 (301) 816-5100 (call collect)

• Report a safety concern:

3/4 (800) 695-7403 3/4 Allegation@nrc.gov

• General information or questions:

3/4 www.nrc.gov 3/4 Select News and Information for a link to email Public Affairs 19

Reference Sources 3/4 Reactor Oversight Process http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html 3/4 Public Electronic Reading Room http://www.nrc.gov/reading-rm.html 3/4 Public Document Room 1-800-397-4209 (Toll Free) 20

NEAC Response and Remarks Millstone Nuclear Power Station Unit & Unit 3 21

End of the Presentation Nuclear Regulatory Commission Region I King of Prussia, Pennsylvania April 17, 2008