ML091740032

Notification of Browns Ferry Nuclear Plant - Component Design Bases Inspection - NRC Inspection Report 0500259-09-008, 05000260-09-008, and 05000296-09-008

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:

Eva Brown, NRR

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