ML072260413
| ML072260413 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/14/2007 |
| From: | Cain L NRC/RGN-II/DRS/EB1 |
| To: | Campbell W Tennessee Valley Authority |
| References | |
| IR-07-007 | |
| Download: ML072260413 (7) | |
See also: IR 05000259/2007007
Text
August 14, 2007
Tennessee Valley Authority
ATTN:
Mr. William R. Campbell
Chief Nuclear Officer and
Senior Vice President
6A Lookout Place
1101 Market Street
Chattanooga, TN 37402-2801
SUBJECT:
NOTIFICATION OF BROWNS FERRY NUCLEAR PLANT COMPONENT
DESIGN BASES INSPECTION - NRC INSPECTION REPORT NOS.
05000259/2007007, 05000260/2007007, AND 05000296/2007007
Dear Mr. Campbell:
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
Plant during the weeks of November 13 - 16, 2007, November 26 - 30, 2007, and December 10 -
14, 2007. The inspection team will be led by Mr. David A. Jones, 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 June 22, 2006.
The inspection will evaluate the capability of risk significant / low margin components to function
as designed and support proper system operation. The inspection will also include a review of
selected operator actions, operating experience, and modifications.
During a telephone conversation on August 7, 2007, Mr. Jones confirmed with Mr. T. Langley 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 October 29 - November 2, 2007
Onsite weeks: November 13 - 16, November 26 - 30, and December 10 - 14,
2007
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. R. Bernhard, a Region II Senior Reactor
Analyst, may accompany Mr. Jones 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
contact Mr. Jones prior to preparing copies of the materials listed in the enclosure and provide
this information to the Region II office by October 15, 2007.
2
The inspectors will try to minimize your administrative burden by specifically identifying only
those documents required for the inspection preparation.
During the information gathering visit, the team leader will also discuss the following inspection
support administrative details: office space, supplemental documents requested to be made
available to the team in the Region II office prior to the inspection preparation week of
November 5 - November 9, 2007; arrangements for site access; and the availability of
knowledgeable plant engineering and licensing personnel to serve as points of contact during
the inspection.
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. Jones at (404) 562-4631 or me at
(404) 562-4876.
Sincerely,
/RA/
Loyd M. Cain, Acting Branch 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 Plant Component Design Basis Inspection
cc w/encl:
Ashok S. Bhatnagar
Senior Vice President
Nuclear Generation Development
and Construction
Tennessee Valley Authority
Electronic Mail Distribution
Preston D. Swafford
Senior Vice President
Nuclear Support
Tennessee Valley Authority
Electronic Mail Distribution
(cc w/encl contd - See page 3)
3
(cc w/encl contd)
Walter M. Justice, II
Interim Vice President
Nuclear Engineering &
Technical Services
Tennessee Valley Authority
Electronic Mail Distribution
Brian J. O'Grady
Site Vice President
Browns Ferry Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
General Counsel
Tennessee Valley Authority
Electronic Mail Distribution
Robert G. Jones, General Manager
Browns Ferry Site Operations
Browns Ferry Nuclear Plant
Tennessee Valley Authority
P. O. Box 2000
Decatur, AL 35609
Beth A. Wetzel, Manager
Corporate Nuclear Licensing and
Industry Affairs
Tennessee Valley Authority
4X Blue Ridge
1101 Market Street
Chattanooga, TN 37402-2801
D. T. Langley, Manager
Licensing and Industry Affairs
Browns Ferry Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
John C. Fornicola, General Manager
Nuclear Assurance
Tennessee Valley Authority
Electronic Mail Distribution
(cc w/encl contd - See page 4)
4
(cc w/encl contd)
Robert H. Bryan, Jr., General Manager
Licensing & Industry Affairs
Tennessee Valley Authority
Electronic Mail Distribution
State Health Officer
Alabama Dept. of Public Health
RSA Tower - Administration
Suite 1552
P. O. Box 303017
Montgomery, AL 36130-3017
Chairman
Limestone County Commission
310 West Washington Street
Athens, AL 35611
Distribution w/encl:
J. Boska, NRR
E. Brown, NRR
L. Raghavan, NRR
RIDSNRRDIRS
PUBLIC
_________________________
OFFICE
RII:DRS
RII:DRS
RII:DRP
SIGNATURE
NAME
BERNHARD
JONES
TLIU
DATE
8/ /2007
8/ /2007
8/14/2007
8/ /2007
8/ /2007
8/ /2007
8/ /2007
E-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO
Enclosure
Browns Ferry Information Request for CDBI
Please provide the information electronically in .pdf files, Excel, or other searchable format on
CDROM. The CDROM should be indexed and hyperlinked to facilitate ease of use. Lists
should contain enough information to be easily understood to someone who has a knowledge
of boiling water reactor technology.
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
copies of your human reliability worksheets for these items.
4.
Any pre-existing evaluation or list of components and calculations 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.).
5.
A list of station applicability evaluations/reviews performed and documented in the station
corrective action program in the past two years for industry events, critical equipment
failures, and safety related equipment vulnerabilities [as communicated by NRC generic
communications, industry communications, 10 CFR part 21 notifications, etc.].
6.
A list of safety related SSC design modifications implemented within the last two years,
sorted by affected system.
7.
This item deleted. Corrective action lists will be requested after the component sample is
determined.
8.
A list of common-cause failure of components that have occurred at Browns Ferry and
have been identified within the last five years.
9.
A list of operability evaluations completed within the last two years, sorted by associated
component or system.
10. Contact information for a person to discuss PRA information prior to the information
gathering trip: name, title, phone number, and e-mail address.
2
Enclosure
11. List of equipment currently 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 those reasons.
12. List of equipment currently in RIS 05-020 (formerly GL 91-18) status.
13. List of equipment currently in MR (a)(1) status.