ML080790674

Slides, NRC Annual Performance Assessment of Three Mile Island - 2007 Reactor Oversight Program.

ML080790674
Person / Time
Site:	Three Mile Island
Issue date:	03/19/2008
From:	Bellamy R NRC/RGN-I/DRP/PB6
To:
BELLAMY, RR
References
Download: ML080790674 (24)

Text

NRC Annual Performance Assessment of Three Mile Island 2007 Reactor Oversight Program

Purpose of Todays Meeting

• Discuss AmerGens Plant Performance for CY 2007

• Provide AmerGen the opportunity to respond to the NRCs Annual Performance Assessment for Three Mile Island and to identify new or existing programs to continue to improve performance

• Provide stakeholders the opportunity to engage the NRC staff on plant performance issues and our role in ensuring safe plant operations 2

Agenda

• Introduction

• NRC Organization and Performance Goals

• Reactor Oversight Process (ROP)

• National Summary of Plant Performance

• Three Mile Islands Plant Performance Assessment

• AmerGens Response and Remarks

• NRC Closing Remarks

• Break

• NRC Available to Address Public Questions 3

Region I Organization Samuel J. Collins Regional Administrator Marc J. 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 Dr. Ronald Bellamy Regional Specialists Branch Chief TMI Resident Inspectors Project Engineers David Kern - Senior RI G. Scott Barber - Senior PE Javier Brand - RI Andrew Rosebrook - PE 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

NRC Values The safe use of radioactive materials and nuclear fuels for beneficial civilian purposes is enabled by the agencys adherence to the principles of good regulations -

3/4 Independence 3/4 Openness 3/4 Efficiency 3/4 Clarity 3/4 Reliability 6

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 7

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 8

Typical Baseline Inspection Areas

• Equipment Alignment

• Maintenance

• Fire Protection

• Operator Response

• Emergency Preparedness

• Radiation and Environmental Monitoring Programs

• Worker Radiation Protection

• Corrective Action Program

• Corrective Action Case Reviews 9

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

• Radiological Effluents Technical Specifications/Offsite Dose Calculation Manual 10

Significance Threshold Performance Indicators 3/4 Green Baseline Inspection 3/4 White May increase 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 11

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 12

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 13

National Summary (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 14

NRC Inspection Activities at Three Mile Island (Jan 1 - Dec 31, 2007)

• 5933 hours0.0687 days <br />1.648 hours <br />0.00981 weeks <br />0.00226 months <br /> of inspection and related activities

• Two resident inspectors on-site

• 16 regional inspections

• Three major team inspections:

Emergency Preparedness Exercise Physical Security Inspection Component Design Basis Inspection 15

Three Mile Island PIs / Findings

• All Performance Indicators were Green for CY2007

• 13 Green or Severity Level-IV inspection findings for CY2007 16

NRC Example Inspection Findings

• Severity Level IV - Deficient Control of Overtime during Refueling Outages

• Several Green Findings during Fall Refueling Outage

- Reactor Vessel Water Level anomaly led to Unusual Event

- Inadequate Reactor Coolant System Vent Area due to deficient work controls

- Damaged Control Rod Assembly during Refueling Bridge Operations

- Damaged Fuel Assembly during Refueling Bridge Operations 17

Three Mile Island Performance Indicators Occupational RETS/ODCM Unplanned Emergency AC RCS Specific Drill/Exercise Security Exposure Control Radiological Scrams (G) Power System (G) Activity (G) Performance (G) (Not Public)

Effectiveness (G) Effluent (G)

Unplanned High Pressure ERO Drill Scrams with Injection System RCS Leakage (G)

Participation (G)

Complications (G) (G)

Residual Heat Alert and Unplanned Power Removal System Notification Changes (G)

(G) System (G)

Heat Removal System (G)

Cooling Water Systems (G)

Safety System Functional Failures (G) 18

NRC Annual Assessment Summary Three Mile Island

• AmerGen operated the plant safely and in a manner that preserved public health and safety and protected the environment.

• TMI was in the Licensee Response column of the NRCs Action Matrix for all four quarters of 2007.

• NRC plans baseline inspections at TMI for the remainder of CY 2008. Additional inspections are planned in the areas of license renewal, and mitigation strategies.

19

Licensee Response and Remarks Mr. Bill Noll Site Vice President - Three Mile Island AmerGen Energy Company LLC 20

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 Public Meetings and Involvement or Contact Us for Public Affairs 21

NRC Representatives

• Dr. Ronald Bellamy , Branch Chief 3/4 (610) 337-5200

• David Kern, Senior Resident Inspector 3/4 (717) 948-1165

• Javier Brand, Resident Inspector 3/4 (717) 948-1165

• G. Scott Barber, Senior Project Engineer 3/4 (610) 337-5232

• Andrew Rosebrook, Project Engineer 3/4 (610) 337-5199 22

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) 23

End of the Presentation Nuclear Regulatory Commission - Region I King of Prussia, Pennsylvania April 3, 2008