ML12293A137
| ML12293A137 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/18/2012 |
| From: | Nease R NRC/RGN-II/DRS/EB1 |
| To: | James Shea Tennessee Valley Authority |
| References | |
| IR-13-007 | |
| Download: ML12293A137 (8) | |
See also: IR 05000259/2013007
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
245 PEACHTREE CENTER AVENUE NE, SUITE 1200
ATLANTA, GEORGIA 30303-1257
October 18, 2012
Mr. Joseph W. Shea
Manager, Corp. Nuclear Licensing Programs
Tennessee Valley Authority
Chattanooga, TN 37402-2801
SUBJECT: NOTIFICATION OF BROWNS FERRY NUCLEAR STATION - COMPONENT
DESIGN BASES INSPECTION - NRC INSPECTION REPORT
05000259/2013007, 05000260/2013007, AND 05000296/2013007
Dear Mr. Shea:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a component design bases inspection at your Browns Ferry Nuclear
Station during the weeks of January 28 - February 1, February 11 - 15, and February 25 -
March 1, 2013. The inspection team will be led by Shakur Walker, a Senior Reactor Inspector
from the NRC's Region II Office. This inspection will be conducted in accordance with the
baseline inspection procedure, Procedure 71111.21, Component Design Bases Inspection,
issued August 14, 2012.
The inspection will evaluate the capability of risk significant / low margin components to function
as designed and to support proper system operation. The inspection will also include a review
of selected operator actions, operating experience, and modifications.
During a telephone conversation on October 15, 2012, Mr. Walker confirmed with Mr. James
Davenport of your staff, arrangements for an information-gathering site visit and the three-week
onsite inspection. The schedule is as follows:
- Information-gathering visit: Week of January 7 - 11, 2013
- Onsite weeks: January 28 - February 1, February 11 - 15, and February 25 - March 1,
2013
The purpose of the information-gathering visit is to meet with members of your staff to identify
risk-significant components and operator actions. Information and documentation needed to
support the inspection will also be identified. Mr. Rudy Bernhard, a Region II Senior Reactor
Analyst, will support Mr. Walker during the information-gathering visit to review probabilistic risk
assessment data and identify risk significant components, which will be examined during the
inspection.
The enclosure lists documents that will be needed prior to the information-gathering visit.
Please provide the referenced information to the Region II office by December 17, 2012.
J. Shea 2
Contact Mr. Walker with any questions concerning the requested information. The inspectors
will try to minimize your administrative burden by specifically identifying only those documents
required for inspection preparation.
Additional documents will be requested during the information-gathering visit. The additional
information will need to be made available to the team in the Region II office prior to the
inspection teams preparation week of January 21. Mr. Walker, will also discuss the following
inspection support administrative details: (1) availability of knowledgeable plant engineering and
licensing personnel to serve as points of contact during the inspection, (2) method of tracking
inspector requests during the inspection, (3) licensee computer access, (4) working space, (5)
arrangements for site access, and (6) other applicable information.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
enclosure will be 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).
Thank you for your cooperation in this matter. If you have any questions regarding the
information requested or the inspection, please contact Mr. Walker at (404) 997-4639 or me at
(404) 997-4530.
Sincerely,
/RA/
Rebecca L. Nease, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-259, 50-260, 50-296
License Nos.: DPR-33, DPR-52, DPR-68
Enclosure:
Information Request for Browns Ferry Nuclear Station -
Component Design Bases Inspection
cc: (See page 3)
_________________________ xG SUNSI REVIEW COMPLETE G FORM 665 ATTACHED
OFFICE RII:DRS RII:DRS
NAME WALKER NEASE
DATE 10/17/2012 10/18/2012 10/ /2012 10/ /2012 10/ /2012 10/ /2012 10/ /2012
E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
J. Shea 3
cc:
K. J. Polson James L. McNees, CHP
Site Vice President Director
Browns Ferry Nuclear Plant Office of Radiation Control
Tennessee Valley Authority Alabama Dept. of Public Health
Electronic Mail Distribution P. O. Box 303017
Montgomery, AL 36130-3017
S. M. Bono
Plant Manager Senior Resident Inspector
Browns Ferry Nuclear Plant U.S. Nuclear Regulatory Commission
Tennessee Valley Authority Browns Ferry Nuclear Plant
Electronic Mail Distribution U.S. Nuclear Regulatory Commission
10833 Shaw Road
James E. Emens Athens, AL 35611-6970
Manager, Licensing
Browns Ferry Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
E. W. Cobey
Manager, Corporate Nuclear Licensing -
Tennessee Valley Authority
Electronic Mail Distribution
T. A. Hess
Program Manager
Corporate Licensing
Tennessee Valley Authority
Electronic Mail Distribution
Edward 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
Letter to Joseph W. Shea from Rebecca L. Nease dated October 18, 2012.
SUBJECT: NOTIFICATION OF BROWNS FERRY NUCLEAR STATION - COMPONENT
DESIGN BASES INSPECTION - NRC INSPECTION REPORT
05000259/2013007, 05000260/2013007, AND 05000296/2013007
Distribution:
RIDSNRRDIRS
PUBLIC
RidsNrrPMBrownsFerry Resource
INFORMATION REQUEST FOR BROWNS FERRY NUCLEARSTATION
COMPONENT DESIGN BASES INSPECTION
Please provide the information electronically in .pdf files, Excel, or other searchable format on
CDROM (or FTP site, Sharepoint, etc.) The CDROM (or website) should be indexed and
hyperlinked to facilitate ease of use.
1. From your most-recent probabilistic safety analysis (PSA) excluding external events and
fires:
a. Two risk rankings of components from your site-specific probabilistic safety
analysis (PSA): one sorted by Risk Achievement Worth (RAW), and the other
sorted by Birnbaum Importance
b. A list of the top 500 cutsets
2. From your most-recent probabilistic safety analysis (PSA) including external events and
fires:
a. Two risk rankings of components from your site-specific probabilistic safety
analysis (PSA): one sorted by Risk Achievement Worth (RAW), and the other
sorted by Birnbaum Importance
b. A list of the top 500 cutsets
3. Risk ranking of operator actions from your site specific PSA sorted by RAW. Provide
human reliability worksheets for these items
4. List of time critical operator actions with a brief description of each action
5. List of Emergency and Abnormal Operating Procedures revised (significant) since
November 1, 2009 with a brief description of each revision
6. List of components with low design margins (i.e., pumps closest to the design limit for flow
or pressure, diesel generator close to design required output, heat exchangers close to
rated design heat removal, MOV risk-margin rankings, etc.) and associated evaluations or
calculations
7. List of station operating experience evaluations/reviews performed and documented in the
stations corrective action program for industry events and safety related equipment
failures/vulnerabilities [as communicated by NRC generic communications, industry
communications, 10 CFR part 21 notifications, etc.] since November 1, 2009
8. List and brief description of safety related SSC design modifications implemented since
November 1, 2009
9. List and brief description of common-cause component failures that have occurred since
November 1, 2009
10. List and brief description of operability evaluations completed since November 1, 2009
Enclosure
2
11. List of equipment on the sites Station Equipment Reliability Issues List, including a
description of the reason(s) why each component is on that list and summaries (if available)
of your plans to address the issue(s)
12. List and brief description of equipment currently in degraded or nonconforming status as
described in RIS 05-020
13. List and reason for equipment classified in maintenance rule (a)(1) status since November
1, 2009 to present
14. Copies of System Descriptions (or the like design basis documents) for Safety-Related
Systems
15. Copy of UFSAR(s)
16. Copy of Technical Specification(s)
17. Copy of Technical Specifications Bases
18. Copy of Technical Requirements Manual(s)
19. List and brief description of Root Cause Evaluations that have been performed since
November 1, 2009
20. In-service Testing Program Procedure(s)
21. Corrective Action Program Procedure(s)
22. One line diagram of electrical plant (electronic and full size - hard copy week of January 7)
23. Index and legend for electrical plant one-line diagrams
24. Primary AC calculation(s) for safety-related buses
25. Primary DC calculation(s) for safety-related buses
26. PI&Ds for ECCS systems (electronic and 1/2 size - hard copy week of January 7)
27. Index and Legend for PI&Ds
28. Copy of design bases documents for ECCS systems
29. Copy of Operability determination procedure(s)
30. Copies of condition reports associated with findings from previous CDBI (if applicable)
31. Index (procedure number, titles, and current revision) of station Emergency Operating
Procedures (EOPs), Abnormal Operating Procedures (AOPs), and Annunciator Response
Procedures (ARPs)
Enclosure
3
32. Copy of any self-assessments performed in preparation for this inspection
33. List of any condition reports generated in preparation for this inspection
34. Contact information for a person to discuss PRA information prior to the information-
gathering trip (name, title, phone number, and e-mail address)
Enclosure