ML080790674
| ML080790674 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 03/19/2008 |
| From: | Ronald Bellamy 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
2 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
3 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
4 Region I Organization Samuel J. Collins Regional Administrator Marc J. Dapas Deputy Regional Administrator David C. Lew Director Division of Reactor Projects James W. Clifford Deputy Director Marsha K. Gamberoni Director Division of Reactor Safety Darrell J. Roberts Deputy Director Regional Specialists Dr. Ronald Bellamy Branch Chief Project Engineers G. Scott Barber - Senior PE Andrew Rosebrook - PE TMI Resident Inspectors David Kern - Senior RI Javier Brand - RI
5 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
6 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
7 Reactor Oversight Process 3 Strategic Areas & 7 Cornerstones Reactor Safety Radiation Safety Safeguards Initiating Events Mitigating Systems Barrier Integrity Emergency Preparedness Occupational Radiation Safety Public Radiation Safety Physical Protection
8 Reactor Oversight Process S afety C o rnerstones B aseline In sp ectio n R esu lts S ig nificance Threshold Actio n M atrix S ig nificance Threshold P erform an ce Indicator R esu lts R egulato ry R espo nse S trategic P erform ance Areas S afety C o rnerstones B aseline In sp ectio n R esu lts S ig nificance Threshold Actio n M atrix S ig nificance Threshold P erform an ce Indicator R esu lts R egulato ry R espo nse S trategic P erform ance Areas
9 Typical Baseline Inspection Areas
- Equipment Alignment
- Maintenance
- Fire Protection
- Operator Response
- Radiation and Environmental Monitoring Programs
- Worker Radiation Protection
- Corrective Action Program
- Corrective Action Case Reviews
10 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
11 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
12 Action Matrix Concept Licensee
Response
Regulatory
Response
Degraded Cornerstone Multiple/Rep.
Degraded Cornerstone Unacceptable Performance
- Increasing Safety Significance
- Increasing NRC Inspection Efforts
- Increasing NRC/Licensee Management Involvement
- Increasing Regulatory Actions
13 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
14 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
15 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
16 Three Mile Island PIs / Findings
- All Performance Indicators were Green for CY2007
- 13 Green or Severity Level-IV inspection findings for CY2007
17 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
18 Three Mile Island Performance Indicators Unplanned Scrams (G)
Unplanned Scrams with Complications (G)
Unplanned Power Changes (G)
Emergency AC Power System (G)
High Pressure Injection System (G)
Residual Heat Removal System (G)
Heat Removal System (G)
Cooling Water Systems (G)
Safety System Functional Failures (G)
RCS Specific Activity (G)
RCS Leakage (G)
Alert and Notification System (G)
ERO Drill Participation (G)
Drill/Exercise Performance (G)
RETS/ODCM Radiological Effluent (G)
Occupational Exposure Control Effectiveness (G)
Security (Not Public)
19 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.
20 Licensee Response and Remarks Mr. Bill Noll Site Vice President - Three Mile Island AmerGen Energy Company LLC
21 Contacting the NRC
- Report an emergency:
3/4(301) 816-5100 (call collect)
- Report a safety concern:
3/4(800) 695-7403 3/4Allegation@nrc.gov
- General information or questions:
3/4www.nrc.gov 3/4Select Public Meetings and Involvement or Contact Us for Public Affairs
22 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
23 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)
End of the Presentation Nuclear Regulatory Commission - Region I King of Prussia, Pennsylvania April 3, 2008