ML11276A025
| ML11276A025 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/03/2011 |
| From: | Office of Public Affairs |
| To: | |
| References | |
| Download: ML11276A025 (14) | |
Text
1 Browns Ferry Nuclear 95003 Part 1 Inspection Public Exit Meeting Browns Ferry Nuclear Station Athens, Al October 3, 2011
2 Agenda
- Introduction
- Inspection Results
- TVA Comments
- NRC Closing Remarks
- NRC available to address public questions
Finding of Red Risk Significance
Background
Residual heat removal (RHR) system flow control valve failure was discovered October 23, 2010 The residual heat removal system is primarily used for low pressure coolant injection during accident conditions and cooling while the reactor is shutdown Basis for Red Significance TVAs fire mitigation strategy Specific fire scenarios assumed unavailability of both low pressure coolant injection loops Automatic valve function was lost 3
4 Process the Red Finding:
- Feb 9, 2011 - NRC issued an apparent violation
- April 4, 2011 - Regulatory Conference was held with Tennessee Valley Authority (TVA)
- May 9, 2011 - NRC issued a Final Significance Determination letter and Notice of Violation
- June 8, 2011 - TVA submitted an appeal of the Red finding
- June 22, 2011 - Region II established an independent panel to review TVAs concerns
- August 16, 2011 - NRC issued a final response following completion of the independent review. TVA was informed that the RED finding was substantiated.
Finding of Red Significance
Performance Assessment for Browns Ferry during last year Q2 2010 Q3 2010 Q4 2010 Q1 2011 Q2 2011 Unit 1 Degraded Cornerstone Multiple Repetitive/ Degraded Cornerstone Finding Yellow Violation of 10 CFR 50 Appendix R III.G.1 & III.G.2 Low Pressure Coolant Injection Valve Failure Unit 2 Degraded Cornerstone Licensee Response Finding Yellow Violation of 10 CFR 50 Appendix R III.G.1 & III.G.2 Unit 3 Degraded Cornerstone Licensee Response Finding Yellow Violation of 10 CFR 50 Appendix R III.G.1 & III.G.2 5
Increased Oversight Inspections
- Supplemental Inspections Conducted in Three Parts (IP 95003)
Part 1 - Component Testing Programs Part 2 - Maintenance Programs Formal 95003 Procedure
- Includes third-party review of safety culture assessment 6
Overview of Part 1 Inspection Inspection conducted September 12th - 23rd, 2011 Team Members:
Bob Orlikowski Mike Farnan John Huang Jared Nadel Lou Lake Inspection Focus Motor Operated Valve(MOV) program Inservice Testing (IST) Program Corrective Action Program (CAP)
Immediate corrective actions taken to address the valve failure Evaluation of impact on equipment reliability 7
Overview of Part 1 Inspection Part 1 inspection scope:
Motor Operated Valve Capability:
Sampled risk significant valves Reviewed MOV Program Scope, Design Calculations, Testing, Trending, Maintenance, and program changes Inservice Testing of Pumps and Valves:
Review IST program Reviewed pump and valve testing Inspect immediate corrective actions Licensee actions to correct the valve failure Extent of condition related to other valves 8
Overview of Part 1 Inspection Results:
MOV, IST, and CAP governing procedures were generally found acceptable Programs generally meet the requirements of the NRCs rules and regulations Several issues were identified in two main areas Programmatic requirements Implementation of the programs One issue was identified involving accuracy of information submitted to the NRC MOV program document Additional observations identified 9
TVA Comments 10
11 Open to the Public
- NRC places a high priority on keeping the public and stakeholders informed of its activities.
- At www.nrc.gov, you can:
- Find public meeting dates and transcripts;
- Read NRC testimony, speeches, press releases, and policy decisions; and
- Access the agencys Electronic Reading Room to find NRC publications and documents.
12 Contacting the NRC
- Report an emergency
- (301) 816-5100 (call collect)
- Report a safety concern
- (800) 695-7403
- Allegation@nrc.gov
- General information or questions
- www.nrc.gov
- Select What We Do for Public Affairs
13 NRC Representatives
- Len Wert, Deputy Regional Administrator for Operations
- Rick Croteau, Division Director, Division of Reactor Projects
- Eugene Guthrie, Branch Chief, Special Project, Browns Ferry
- Thierry Ross, Senior Resident Inspector
- Craig Kontz, Senior Project Engineer, Special Project, Browns Ferry
14 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)