ML103550247
| ML103550247 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry |
| Issue date: | 12/21/2010 |
| From: | Eugene Guthrie Reactor Projects Region 2 Branch 6 |
| To: | Krich R Tennessee Valley Authority |
| References | |
| Download: ML103550247 (31) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 December 21, 2010 Mr. Rod Krich Vice President Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
REGULATORY PERFORMANCE MEETING
SUMMARY
- BROWNS FERRY NUCLEAR PLANT, DOCKET NOS. 50-259, 50-260 AND 50-296
Dear Mr. Krich:
This refers to the meeting conducted on December 14, 2010, in Athens, AL. The purpose of this meeting, was to discuss corrective actions associated with the one White finding and one Yellow violation that were documented in NRC Inspection Report 05000259/2010007, 05000260/2010007, and 05000296/2010007. The findings dealt with inadequate safe shutdown instruction entry conditions for Appendix R fire events and failure to ensure one train of cables of systems necessary to achieve and/or maintain post-fire safe shutdown is free of fire damage.
The information presented during the meeting is enclosed.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room (PDR) or from the Publicly Available Records (PARS) component of NRCs 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 Projects Branch 6 Division of Reactor Projects Docket Nos.: 50-259, 50-260, and 50-296 License Nos.: DRP-33, DRP-52, and DRP-68
Enclosures:
As Stated cc w/encl: (See page 2)
G SUNSI REVIEW COMPLETE OFFICE RII:DRP RII:DRP SIGNATURE JDH /RA/
EFG /RA/
NAME JHamman EGuthrie DATE 12/20/2010 12/21/2010 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 Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 C.J. Gannon General Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 J. E. Emens Manager, Licensing and Industry Affairs Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 E. J. Vigluicci Assistant General Counsel Tennessee Valley Authority 6A West Tower 400 West Summit Hill Drive Knoxville, TN 37902 State Health Officer Alabama Dept. of Public Health RSA Tower - Administration Suite 1552 P.O. Box 30317 Montgomery, AL 36130-3017 Chairman Limestone County Commission 310 West Washington Street Athens, AL 35611 James L. McNees, CHP Director Office of Radiation Control Alabama Dept. of Public Health P. O. Box 303017 Montgomery, AL 36130-3017
TVA 3
Letter to R. M. Krich from Eugene Guthrie dated December 21, 2010
SUBJECT:
REGULATORY PERFORMANCE MEETING
SUMMARY
- BROWNS FERRY NUCLEAR PLANT, DOCKET NOS. 50-259, 50-260 AND 50-296 Distribution w/encl:
C. Evans, RII L. Douglas, RII OE Mail RIDSNRRDIRS PUBLIC RidsNrrPMBrownsFerry Resource
Browns Ferry Public Meeting Attendee List PARTICIPANTS:
NRC L. Wert, Director, Reactor Projects E. Guthrie, Chief, Reactor Projects Branch 6, DRP K. ODonohue, Chief, Construction Inspection Branch 2, DCI T. Ross, Senior Resident Inspector, Browns Ferry Nuclear Plant P. Neibaum, Resident Inspector, Browns Ferry Nuclear Plant L. Pressley, Resident Inspector, Browns Ferry Nuclear Plant R. Rodriguez, Senior Reactor Inspector, Division of Reactor Safety J. Ledford, Region II Public Affairs Officer Tennessee Valley Authority K. Polson, Site Vice President, Browns Ferry Nuclear Plant T. Marlow, Director of Safety and Licensing, Browns Ferry Nuclear Plant C. Gannon, General Manager of Operations, Browns Ferry Nuclear Plant J. Emens, Manager, Licensing and Industry Affairs, Browns Ferry Nuclear Plant H. Lee, Corporate Licensing Engineer R. Golden, Senior Manager, Nuclear Communications A. Reagan, Communications Specialist, Browns Ferry Nuclear Plant J Nesbit, Communications Specialist, Browns Ferry Nuclear Plant Media B. Jett, Reporter, WHNT E. Fleischauer, Reporter, Decatur Daily W. Freebairn, Senior Editor, Platts Nucleonics Week Members of the Public C. Beasley S. Horn
1 Browns Ferry Nuclear Station Regulatory Performance Meeting Nuclear Regulatory Commission - Region II Athens, AL December 14, 2010
2 Purpose of Todays Meeting
- A public forum for discussion of the licensees performance.
- Discuss the results of the recent inspection, Inspection For One Degraded Cornerstone Or Any Three White Inputs In a Strategic Performance Area, 95002.
3 Agenda
- Introduction
- Overview of NRC Mission
- Review of Reactor Oversight Process
- Discussion of Plant Performance Results
- Licensee Discussion of Corrective Actions
- Supplemental 95002 Inspection Results
- TVA Comments
- NRC Closing Remarks
- NRC available to address public questions
4 Region II Organization Luis Reyes Regional Administrator Victor McCree Deputy Regional Administrator Division of Reactor Projects Len Wert, Director William Jones, Deputy Director Projects Branch 6 Eugene Guthrie, Chief (404) 997-4662 Resident Inspectors (RI)
Thierry Ross, Senior RI Phillip Niebaum RI Charles Stancil, RI Lundy Presley RI Office: (256) 729-6196 Project Engineers (PE)
Craig Kontz, Senior PE Jeff Hamman, PE Division of Reactor Safety Joel Munday, Director Harold Christensen, Deputy Director Regional Specialist Inspectors
5 Our Mission
- To license and regulate the nations civilian use of byproduct, source, and special nuclear materials to ensure adequate protection of public health and safety, promote the common defense and security, and protect the environment.
6 What NRC Regulates
- Nuclear reactors - commercial power reactors, research and test reactors, new reactor designs
- Nuclear materials - nuclear reactor fuel, radioactive materials for medical, industrial, and academic use
- Nuclear waste - transportation, storage and disposal of nuclear material and waste, decommissioning of nuclear facilities
- Nuclear security - physical security of nuclear facilities and materials from sabotage or attacks
7 Reactor Oversight Process Safety Cornerstones Baseline Inspection Results Significance Threshold Action Matrix Significance Threshold Performance Indicator Results Regulatory Response Strategic Performance Areas Safety Cornerstones Baseline Inspection Results Significance Threshold Action Matrix Significance Threshold Performance Indicator Results Regulatory Response Strategic Performance Areas
8 Significance Threshold Performance Indicators Green:
Only Baseline Inspection White:
Increases NRC oversight Yellow:
Increases NRC oversight Red:
Increases NRC oversight Inspection Findings Green:
Very low safety issue White:
Low to moderate safety issue Yellow:
Substantial safety issue Red:
High safety issue
9 Action Matrix Concept Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions Licensee
Response
Regulatory
Response
(95001)
Degraded Cornerstone (95002)
Multiple/Rep Degraded Cornerstone (95003)
Unacceptable Performance
Operating Assessment for Browns Ferry Q4 2009 Q1 2010 Q2 2010 Q3 2010 Q4 2010 Unit 1 Degraded Cornerstone Degraded Cornerstone Degraded Cornerstone Degraded Cornerstone Degraded Cornerstone Licensee
Response
Yellow Violation of 10 CFR 50 Appendix R III.G.1 & III.G.2 Yellow Violation of 10 CFR 50 Appendix R III.G.1 & III.G.2 Yellow Violation of 10 CFR 50 Appendix R III.G.1 & III.G.2 Yellow Violation of 10 CFR 50 Appendix R III.G.1 & III.G.2 Unit 2 Degraded Cornerstone Degraded Cornerstone Degraded Cornerstone Degraded Cornerstone Degraded Cornerstone Licensee
Response
Yellow Violation of 10 CFR 50 Appendix R III.G.1 & III.G.2 Yellow Violation of 10 CFR 50 Appendix R III.G.1 & III.G.2 Yellow Violation of 10 CFR 50 Appendix R III.G.1 & III.G.2 Yellow Violation of 10 CFR 50 Appendix R III.G.1 & III.G.2 Unit 3 Degraded Cornerstone Degraded Cornerstone Degraded Cornerstone Degraded Cornerstone Degraded Cornerstone Licensee
Response
Yellow Violation of 10 CFR 50 Appendix R III.G.1 & III.G.2 Yellow Violation of 10 CFR 50 Appendix R III.G.1 & III.G.2 Yellow Violation of 10 CFR 50 Appendix R III.G.1 & III.G.2 Yellow Violation of 10 CFR 50 Appendix R III.G.1 & III.G.2 10
Assessment Results - Units 1,2 & 3 4th Quarter 2009, 1st, 2nd & 3rd Quarters 2010 within Degraded Cornerstone Column One Yellow Violation in the Mitigating Systems Cornerstone One White Violation in the Mitigating Systems Cornerstone 4th Quarter 2010 Follow-up inspection per IP 95002 was completed in October 2010 Assessment following closure of One Yellow Violation and one White Finding in the Mitigating Systems Cornerstone determined that performance returned to the Licensee Response Column as of November 2010.
11
95002 Supplemental Inspection IP 95002 Inspection Team
- Kathleen ODonohue, Branch Chief, Team Leader
- John Hanna, Sr. Reactor Analyst
- Molly Keefe, Human Factors Specialist
- Robert Monk, Sr. Resident Inspector, Watts Bar
- Reinaldo Rodriguez, Sr. Reactor Inspector 12
95002 Supplemental Inspection
- The 95002 was completed the week of October 22, 2010
- Total of 210 Direct Inspection Hours The inspection reviewed:
- Yellow Violation of 10 CFR 50 Appendix R III.G.1 & III.G.2
- White Violation of Technical Specification 5.4.1.a.
13 G1
95002 Supplemental Inspection IP 95002 Inspection Objectives
- Assurance that the root and contributing causes are understood
- Assurance that the corrective actions are sufficient to:
(1) address root causes and (2) prevent recurrence 14
95002 Supplemental Inspection IP 95002 Inspection Objectives, cont.
- Independent inspection of licensees root cause and extent of condition
- Independent assessment of possible collective risk-significant performance issues
- Independent determination of safety culture component contribution to performance issues 15
95002 Supplemental Inspection
- The NRC inspection team determined that the following inspection objectives were satisfied:
Assurance that the root and contributing causes were understood Assurance that the corrective actions, both completed and planned, for the performance issues were sufficient to address the root and contributing causes and prevent recurrence 16
95002 Supplemental Inspection 17 Assurance that the root and contributing causes were understood:
Yellow Violation of 10 CFR 50 Appendix R III.G.1 & II.G.2
- 1 - Inadequate management and oversight of the BFN App R program
- 2 - Ineffective use of the Corrective Action program Contributing Cause: Ineffective turn-over from BFN Start-up Team to BFN Station Staff
95002 Supplemental Inspection Assurance that the root and contributing causes were understood:
- White Violation of Technical Specification 5.4.1.a.
- 1 - Inadequate preparation and review of procedure revision Contributing cause: inadequate procedure revision guidance 18
95002 Supplemental Inspection Assurance that the corrective actions for the performance issues were sufficient to address the root and contributing causes and prevent recurrence:
Corrective actions, both completed and in progress are sufficient to address the root and contributing causes and to prevent recurrence.
Success depends on management oversight:
Organizational Restructure/Follow-up CA Team 19
95002 Supplemental Inspection
- Independent Assessment of extent of cause/condition
- No issues identified for BFN
- Independent Assessment of Safety Culture at Browns Ferry Nuclear Plant
- Safety Culture determined to be improving 20
21 Assessment Summary
- Overall, Browns Ferry performance was determined to be in the Degraded Cornerstone of the NRCs Action Matrix Given a satisfactory 95002 inspection and no additional inputs, all three Units have returned to the Licensee Response Column on the NRCs Action Matrix, during the 4th Qtr CY 2010
TVA Comments
- TVA Management Comments/Presentation 22
23 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.
24 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
25 NRC Representatives
- Leonard Wert, Division Director
- Eugene Guthrie, Branch Chief
- Thierry Ross, Senior Resident Inspector
- Charles Stancil, Resident Inspector
- Phillip Niebaum, Resident Inspector
- Lundy Presley, Resident Inspector
- Roger Hannah, Senior Public Affairs Officer (404) 997-4417
26 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)