ML112450385
| ML112450385 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/02/2011 |
| From: | Eugene Guthrie Division Reactor Projects II |
| To: | Krich R Tennessee Valley Authority |
| References | |
| EA-11-018 | |
| Download: ML112450385 (39) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 September 2, 2011 EA-11-018 Mr. R. M. Krich Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801
SUBJECT:
PUBLIC MEETING
SUMMARY
FOR BROWNS FERRY NUCLEAR PLANT, DOCKET NO. 50-259
Dear Mr. Krich:
This refers to the public meeting conducted on August 30, 2011, in Atlanta, GA. The purpose of this meeting was to allow Browns Ferry Nuclear Plant Unit 1 and representatives of Tennessee Valley Authority (TVA) to meet with U. S. Nuclear Regulatory Commission (NRC) staff to discuss the NRCs plans for implementing supplemental inspections in accordance with Inspection Procedure 95003, Supplemental Inspection for Repetitive Degraded Cornerstones, Multiple Degraded Cornerstones, Multiple Yellow Inputs, or One Red Input, at the Browns Ferry Nuclear Plant.
A list of attendees and a copy of the presentation handouts are enclosed.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Should you have any questions concerning this meeting, please contact me at (404) 997-4662.
Sincerely,
/RA/
Eugene F. Guthrie, Chief Special Project, Browns Ferry Division of Reactor Projects Docket No.:
50-259 License No.: DRP-33
Enclosure:
As stated cc w/encl: (See page 2)
___ ML112450385 _
X SUNSI REVIEW COMPLETE OFFICE RII:DRP RII:DRP SIGNATURE CRK /RA/
EFG /RA/
NAME CKontz EGuthrie DATE 09/02/2011 09/02/2011 E-MAIL COPY?
YES NO YES NO YES NO YES NO YES NO YES NO YES NO
TVA 2
cc w/encl:
K. J. Polson Site Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution C.J. Gannon General Manager Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution J. E. Emens Manager, Licensing Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution T. C. Matthews Manager, Corporate Nuclear Licensing - BFN Tennessee Valley Authority Electronic Mail Distribution E. J. Vigluicci Assistant General Counsel Tennessee Valley Authority Electronic Mail Distribution Chairman Limestone County Commission 310 West Washington Street Athens, AL 35611 Donald E. Williamson State Health Officer Alabama Dept. of Public Health RSA Tower - Administration Suite 1552 P.O. Box 30317 Montgomery, AL 36130-3017 James L. McNees, CHP Director Office of Radiation Control Alabama Dept. of Public Health P. O. Box 303017 Montgomery, AL 36130-3017
3 Letter to R. M. Krich from Eugene F. Guthrie dated September 2, 2011
SUBJECT:
PUBLIC MEETING
SUMMARY
FOR BROWNS FERRY NUCLEAR PLANT, DOCKET NO. 50-259 Distribution w/encl:
C. Evans, RII L. Douglas, RII OE Mail RIDSNRRDIRS PUBLIC RidsNrrPMBrownsFerry Resource
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 Browns Ferry Public Meeting Atlanta, GA August 30, 2011 Name (Print)
___Blake Farmer ____________________
___Thomas Saporito _________________
___Glenn Carroll____________________
Title and Organization Nashville Public Radio Saprodani-Associates ______ _________
Nuclear Watch South _ ___________
2 NRC ATTENDEES V. McCree, Regional Administrator, Region II L. Wert, Deputy Regional Administrator, Region II R. Croteau, Director, Division of Reactor Projects (DRP), Region II W. Jones, Deputy Director, DRP, Region II E. Guthrie, Chief, Special Project, Browns Ferry, DRP, RII C. Kontz, Senior Project Engineer, Special Project, Browns Ferry, DRP, RII T. Ross, Senior Resident Inspector, Browns Ferry, DRP, RII R. Orlikowski, Project Engineer, Reactor Project Branch 1, DRP, RIII M. Keefe, Human Factors Specialist, NRR, HQ L. Lake, Senior Reactor Inspector, DRS, RII
3
1 Browns Ferry Nuclear 95003 Implementation Public Meeting Nuclear Regulatory Commission - Region II Atlanta, Ga August 30, 2011
2 Agenda
- Introduction
- Overview of 95003 inspection
- TVA Comments
- Conduct of 95003 inspection
- NRC Closing Remarks
- NRC available to address public questions
Finding of Red Risk Significance
Background
- Residual heat removal (RHR) system flow control valve failed October 23, 2010 operators found that the valve would not pass flow when the subsystem was attempted to be placed in service the flow control portion of the valve, called the disc, was found stuck in the seat of the valve the disc had become separated from the stem and could no longer be controlled by the valve motor operator
- The residual heat removal system is primarily used for low pressure coolant injection during accident conditions and cooling while the reactor is shutdown 3
Finding of Red Significance Basis for Red Significance TVAs fire mitigation strategy resulted in a significant increase in the core damage frequency This strategy limits the availability of alternative sources of reactor coolant inventory makeup Both Loops were unavailable based on accident scenarios Two residual heat removal system loops are normally available.
Automatic valve function was lost Including the ability of plant operators to manually use this loop of the subsystem 4
5 Sequence of Events to Process the Red Finding:
- NRC issued an apparent violation on Feb 9, 2011 Failure of the residual heat removal system to meet the Technical Specification operating requirements
- Regulatory Conference was held with Tennessee Valley Authority (TVA) on April 4, 2011 Discuss the apparent violation and risk significance of the issue
- NRC issued a Final Significance Determination letter to TVA on May 9, 2011 Red finding and Notice of Violation was substantiated Finding of Red Significance
Finding of Red Significance Sequence of Events Continued:
TVA submitted an appeal on June 8, 2011, to the Red finding Concerned that the performance deficiency had changed since the Regulatory Conference discussions Region II established an independent panel June 22, 2011 to review TVAs concerns TVA was informed they did not meet criteria for an appeal NRC issued the follow-up to the independent review panel on August 16, 2011 TVA was informed that the NRCs final determination on the RED finding was substantiated 6
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 7
95003 Overview What happens next?
- Red significance will warrant further NRC inspection Supplemental Inspection Inspection Procedure 95003, Supplemental Inspection For Repetitive Degraded Cornerstones, Multiple Degraded Cornerstones, Multiple Yellow Inputs Or One Red Input 8
95003 Inspection Overview
- A comprehensive, diagnostic supplemental inspection
- Review of programs and processes not inspected as part of the baseline inspection program
- Focus of inspection effort will encompass equipment reliability 9
95003 Overview of Inspection
- Inspection Results will evaluate corrective actions taken
- Determine acceptability or need for additional action
- Assessment of safety culture Validation of TVAs root cause evaluation Validation of TVAs third party safety culture assessment 10
95003 Overview of Inspection
- The inspection will be conducted in three parts:
Part 1 and Part 2 will be performed without the licensees formal statement of readiness Part 3 will be performed after TVA has formally informed the NRC that they are ready for the inspection Safety Culture assessment will be performed in parallel with the inspection efforts.
11
12 Division of Reactor Projects Rick Croteau, Director William Jones, Deputy Director Special Projects Branch Eugene Guthrie, Chief 95003 Team Lead (404) 997-4662 Individual Inspection Team Focus Area Leads Assistant 95003 Team Lead TBD Senior Project Engineer Craig Kontz, Senior PE (404) 997-4715 Resident Inspectors (RI)
Thierry Ross, Senior RI Charles Stancil, RI Phillip Niebaum, RI Lundy Pressley, RI RI Office: (256) 729-6196 Region II Reorganization
TVA Comments 95003 Implementation 13
95003 Overview of Inspection
- Part 1 Inspection On-site inspection September 12 through September 23 Four Team Members
- Team Lead - Robert Orlikowski, RIII
- Team members - Head Quarters and RII Focus on testing programs, including valve testing
- in-service testing programs (IST), the motor operated valve (MOV) testing program, and the corrective action program (CAP)
- broader extent of condition aspects of testing programs used to comply with technical specifications and other regulatory requirements 14
95003 Overview of Inspection
- Part 2 Inspection Inspection activities October through December Five Member Team Focus on the Maintenance Program Based on historical issues with equipment reliability All phases of maintenance on selected safety-related equipment will be inspected and assessed 15
95003 Overview of Inspection
- Part 3 - Formal Part of 95003 Inspection Overall Inspection Focus - Equipment Reliability Strategic Area Focus - Reactor Safety Program Review Focus Areas
- Maintenance
- Operations
- Engineering
- Corrective Action
- Management Oversight/Decision Making Team Structure 16
95003 Overview of Inspection
- Safety Culture Assessment Review and assessment of the licensees third-party, independent assessment of Nuclear Safety Culture Graded assessment of the licensees safety culture based on the results of the evaluation 17
18 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.
19 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
20 NRC Representatives
- Victor McCree, RII, Regional Administrator
- 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
21 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)
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 1 Meeting with NRC Preparation for NRC Inspection Procedure 95003 Inspection Atlanta, Georgia August 30, 2011
Agenda Introduction Response Overview Inspection Preparation Summary Preston Swafford Keith Polson Tim Cleary Preston Swafford 1
Introduction An undetected failure of valve 1-FCV-74-66 to open resulted in a finding with Red safety significance. The NRC therefore moved Browns Ferry, Unit 1, into Column 4 of the Action Matrix, which requires NRC inspections per Inspection Procedure (IP) 95003.
TVA has created an Inspection Response Team to prepare for the 95003 inspection activities.
Using the best available internal and industry expertise, we will take all actions necessary to meet or exceed IP 95003 inspection criteria, to return Browns Ferry, Unit 1, to Column 1, Licensee Response, of the Action Matrix.
2
Response Overview We recognize that, while improvements in equipment reliability are being made, the pace of these improvements needs to be accelerated.
TVA has extensive preparations for these inspections in progress. Our root cause analysis team is identifying the underlying causes and contributors for this event.
- We are continuing to look at the implementation of the Inservice Testing Program and the Motor-Operated Valve Program from the time of Generic Letter 89-10.
We recognize the need to include an evaluation of actions being taken to resolve Substantive Cross-Cutting Issues in thorough evaluations of identified problems and appropriate and timely corrective actions, to identify any further enhancements.
Comprehensive corrective actions are being developed, and form the basis of the Integrated Improvement Plan.
3
Historical Data Review Site Initiatives Root Cause IA&CPD 95003 Inspection Key Attribute Review NRC Confirmation of Required Actions P1c, P1d Safety Culture Assessment 95002 Data Gather and Analysis Topical Areas - Analysis and Actions Corrective Action Implementation and Long-Term Sustainability BFN Integrated Improvement Plan Project Phases Action Plans Backlog Reviews Update Plan Collective Evaluation Cause Analysis Inspection Report NRC Inspections Closure Review Boards Response Overview (continued) 4 READY FOR INSP.
Attributes Corporate Driven - dedicated leadership provided to project Site Engagement - key leaders and staff assigned to project full time Strong Licensing Component - coordinated site and corporate regulatory interface External Support - external resources and expertise utilized on all aspects of project Oversight - NSRB, QA, MRM, and Review Boards being utilized Communication Support - project support from site and corporate Project Scope - broader than minimum requirements of Inspection Procedure 95003 5
Inspection Preparation
Focus Areas Comprehensive Root Cause Analysis for why valve 1-FCV-74-66 Failure was not detected*
Identification, Assessment, and Correcting Performance Deficiencies Review*
Performance Around Reactor Safety for Mitigating Systems*
Third Party Independent Safety Culture Assessment*
Historical Document Review (at least five years back)
Collective evaluation and causal analysis for underlying issues Implement corrective actions resulting from causal analysis
- Inspection Procedure 95003 Attributes Inspection Preparation (continued) 6
Safety Culture Assessment Third Party Independent Safety Culture Assessment IP 95003 attributes will be addressed.
Conducted by SYNERGY SYNERGY has conducted the last two safety culture surveys for the TVA nuclear operating fleet (2006 and 2009).
In addition to the standard safety culture surveys, SYNERGY will perform a more in-depth assessment of the safety culture at Browns Ferry.
Safety Culture Assessment Schedule Survey to begin September 19 and continue for approximately two weeks.
The Assessment activities will be completed by about mid-December.
Final Assessment Report is expected to be available by the end of January 2012.
Inspection Preparation (continued) 7
Resources and Schedule Personnel
- Core TVA Team - 15 to 20 employees
- Contract Support - 20 to 80 individuals during the various phases of the project Schedule Duration
- Data Gather and Analysis - Now through November 2011
- Topical Areas - Analysis and Actions - November through the NRC inspection
- Corrective Action Implementation - January 2012 through completion of required actions 8
Inspection Preparation (continued)
9 Inspection Preparation (continued)
Response Team
TVA understands the actions required for effective preparations for the 95003 inspection.
TVA is applying the appropriate resources to this effort to ensure that Browns Ferry will be ready for the inspection.
We are using this opportunity to look beyond the issues associated with the NRC finding and accelerate overall improvement at the Browns Ferry plant.
Summary 10