ML091740032
| ML091740032 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/22/2009 |
| From: | Binoy Desai Engineering Region 1 Branch 1 |
| To: | Swafford P Tennessee Valley Authority |
| References | |
| IR-09-008 | |
| Download: ML091740032 (4) | |
See also: IR 05000259/2009008
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
SAM NUNN ATLANTA FEDERAL CENTER
61 FORSYTH STREET, SW, SUITE 23T85
ATLANTA, GEORGIA 30303-8931
June 22, 2009
Mr. Preston D. Swafford
Chief Nuclear Officer and Executive Vice President
Tennessee Valley Authority
3R Lookout Place
1101 Market Street
Chattanooga, TN 37402-2801
SUBJECT: NOTIFICATION OF BROWNS FERRY NUCLEAR PLANT - COMPONENT
DESIGN BASES INSPECTION - NRC INSPECTION REPORT
05000259/2009008, 05000260/2009008, AND 05000296/2009008
Dear Mr. Swafford:
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 period of September 28 - November 20, 2009. The inspection team will be led
by Mr. Robert Berryman, 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 19, 2008.
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 June 18, 2009, Mr. Berryman confirmed, with Mr. Jim
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 September 28-October 2, 2009.
- Onsite weeks: Weeks of October 19 - 23, November 2 - 6, and November 16 - 20, 2009.
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 and gathered or requested. Mr. Walt Rogers, a
Region II Senior Reactor Analyst, may accompany Mr. Berryman during the information
gathering visit to review probabilistic risk assessment data and identify risk significant
components which will be examined during the inspection.
TVA 2
The enclosure lists documents that will be needed prior to the information gathering visit. Please
contact Mr. Berryman with any questions prior to preparing materials listed in the enclosure and
provide the referenced information to the Region II office by September 15, 2009. 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; site, plant and information system access; required
resources; and information exchange protocol.
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. Berryman at (404) 562-4817 or me
at (404) 562-4519.
Sincerely,
/RA/
Binoy B. Desai, 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 Plant Component Design Bases
Inspection
cc w/encl: (See page 3)
_________________________ SUNSI REVIEW COMPLETE
OFFICE RII:DRS RII:DRS
SIGNATURE /RA/ /RA/
NAME R. Berryman B. Desai
DATE 06/22/2009 06/22/2009
E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
TVA 3
cc w/encls: General Counsel
Ashok S. Bhatnagar, Senior VP Tennessee Valley Authority
Nuclear Generation Development and Electronic Mail Distribution
Construction
Tennessee Valley Authority Larry E. Nicholson, General Manager
Electronic Mail Distribution Performance Improvement
Tennessee Valley Authority
Preston D. Swafford Electronic Mail Distribution
Chief Nuclear Officer and Executive VP
Tennessee Valley Authority Michael A. Purcell
Electronic Mail Distribution Senior Licensing Manager
Nuclear Power Group
William R. Campbell, Senior VP Tennessee Valley Authority
Fleet Engineering Electronic Mail Distribution
Tennessee Valley Authority
6A Lookout Place Michael J. Lorek, Vice President
1101 Market Place Nuclear Engineering & Projects
Chattanooga, TN 37402-2801 Tennessee Valley Authority
Electronic Mail Distribution
Thomas Coutu, Vice President
Nuclear Support Fredrick C. Mashburn, Acting Manager
Tennessee Valley Authority Corporate Nuclear Licensing and Industry
Electronic Mail Distribution Affairs
Tennessee Valley Authority
R. G. (Rusty) West, Site Vice President Electronic Mail Distribution
Browns Ferry Nuclear Plant
Tennessee Valley Authority Senior Resident Inspector
Electronic Mail Distribution Browns Ferry Nuclear Plant
U.S. Nuclear Regulatory Commission
Frederick Russell Godwin 10833 Shaw Road
Manager, Licensing and Industry Affairs Athens, AL 35611-6970
Browns Ferry Nuclear Plant
Tennessee Valley Authority Kirksey E. Whatley, Director
P.O. Box 2000 Office of Radiation Control
Decatur, AL 35609 Alabama Dept. of Public Health
Electronic Mail Distribution
James J. Randich, Plant Manager
Browns Ferry Nuclear Plant Chairman
Tennessee Valley Authority Limestone County Commission
P.O. Box 2000 310 West Washington Street
Athens, AL 35611
Ludwig E. Thibault, General Manager
Nuclear Oversight & Assistance Dr. D. E. Williamson
Tennessee Valley Authority State Health Officer
3R Lookout Place Alabama Dept. of Public Health
1101 Market Street Electronic Mail Distribution
Chattanooga, TN 37402-2801
TVA 4
Letter to Preston D. Swafford from Binoy B. Desai, dated June 22, 2009
SUBJECT: NOTIFICATION OF BROWNS FERRY NUCLEAR PLANT - COMPONENT
DESIGN BASES INSPECTION - NRC INSPECTION REPORT
05000259/2009008, 05000260/2009008, AND 05000296/2009008
Distribution w/encl:
PUBLIC
RidsNrrPMBrownsFerry Resource
Institute of Nuclear Power Operations (INPO)
INFORMATION REQUEST FOR BROWNS FERRY NUCLEAR PLANT
COMPONENT DESIGN BASES INSPECTION
Please provide the information electronically in .pdf files, Excel, or other searchable format on
CDROM. The CDROM should be indexed and possibly hyperlinked to facilitate ease of use.
Information in lists should contain enough information to be easily understood to someone who
has knowledge of pressurized water reactor technology.
1. From your most recent probabilistic safety analysis (PSA) excluding external events and
fires, please provide:
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, please provide:
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 operability evaluations completed within the last two years, sorted by associated
component or system.
7. A list of common-cause failures of components that have occurred at Browns Ferry
Nuclear Plant and have been identified within the last five years.
8. A list of equipment currently planned for upgrade/improvement by the site (e.g. ONE
List), including a description of the reason(s) why each component (i.e. not a
programmatic or system level concern) is on that list and summaries (if available) of your
plans to address those reasons.
9. A list of equipment currently in RIS 05-020 (formerly GL 91-18) status, or in MR (a)(1)
status.
10. Contact information for a person to discuss PRA information prior to the information
gathering trip: name, title, phone number, and e-mail address.
Enclosure