ML070730078

Notification of Sequoyah Nuclear Plant - Component Design Bases Inspection (CDBI) - NRC Inspection Report 05000327-07-006 and 05000328-07-006 and Information Request for CDBI

ML070730078
Person / Time
Site:	Sequoyah
Issue date:	03/13/2007
From:	Cain L NRC/RGN-II/DRS/EB1
To:	Singer K Tennessee Valley Authority
References
IR-07-006
Download: ML070730078 (5)

See also: IR 05000327/2007006

Text

March 13, 2007

Tennessee Valley Authority

ATTN: Mr. Karl W. Singer

Chief Nuclear Officer and

Executive Vice President

6A Lookout Place

1101 Market Street

Chattanooga, TN 37402-2801

SUBJECT: NOTIFICATION OF SEQUOYAH NUCLEAR PLANT - COMPONENT DESIGN

BASES INSPECTION - NRC INSPECTION REPORT 05000327/2007006 AND

05000328/2007006

Dear Mr. Singer:

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 Sequoyah Nuclear

Plant during the weeks of June 4-8, 2007, June 18-22, 2007, and July 9-13, 2007. The

inspection team will be led by Mr. Ryan Taylor, 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 March 13, 2007, Mr. R. Moore confirmed with

Mr. R. Proffitt 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 May 14-18, 2007

• Onsite weeks: June 4-8, 2007, June 18-22, 2007, and July 9-13, 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. Rudy Bernhard, a Region II Senior Reactor

Analyst, may accompany Mr. Taylor 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. Taylor prior to preparing copies of the materials listed in the enclosure and provide

this information to the Region II office by April 30, 2007.

TVA 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

May 28 - June 1, 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. Taylor at (404) 562-4568 or me at

(404) 562-4876.

Sincerely,

/RA/

L.M. Cain, Acting Branch Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.:50-327, 50-328

License Nos.:DPR-77, DPR-79

Enclosure: Information Request for Sequoyah Nuclear Plant

Component Design Bases Inspection

cc w/encl:

TVA 3

Ashok S. Bhatnagar Robert H. Bryan, Jr., General Manager

Senior Vice President Licensing and Industry Affairs

Nuclear Operations Sequoyah Nuclear Plant

Tennessee Valley Authority Tennessee Valley Authority

Electronic Mail Distribution 4X Blue Ridge

1101 Market Street

Preston D. Swafford Chattanooga, TN 37402-2801

Senior Vice President

Nuclear Support David A. Kulisek, Plant Manager

Tennessee Valley Authority Sequoyah Nuclear Plant

Electronic Mail Distribution Tennessee Valley Authority

Electronic Mail Distribution

Larry S. Bryant, Vice President

Nuclear Engineering & Lawrence E. Nanney, Director

Technical Services TN Dept. of Environment & Conservation

Tennessee Valley Authority Division of Radiological Health

Electronic Mail Distribution Electronic Mail Distribution

Randy Douet County Mayor

Site Vice President Hamilton County Courthouse

Sequoyah Nuclear Plant Chattanooga, TN 37402-2801

Electronic Mail Distribution

Ann Harris

General Counsel 341 Swing Loop

Tennessee Valley Authority Rockwood, TN 37854

Electronic Mail Distribution

James H. Bassham, Director

John C. Fornicola, General Manager Tennessee Emergency Management

Nuclear Assurance Agency

Tennessee Valley Authority Electronic Mail Distribution

Electronic Mail Distribution

Glenn W. Morris, Manager

Licensing and Industry Affairs

Sequoyah Nuclear Plant

Tennessee Valley Authority

Electronic Mail Distribution

Beth A. Wetzel, Manager

Corporate Nuclear Licensing and

Industry Affairs

Tennessee Valley Authority

4X Blue Ridge

1101 Market Street

Chattanooga, TN 37402-2801

_________________________

OFFICE RII:DRS RII:DRS RII:DRP RII:DRS

SIGNATURE /RA/ /RA/ /RA/ /RA/

NAME RBernhard RMoore MWidmann RTaylor

DATE 3/13/2007 3/13/2007 3/13/2007 3/13/2007

E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO

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 pressurized 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 Sequoyah 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

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.

Enclosure