ML13098A141

Notification of Sequoyah Nuclear Plant - Component Design Bases Inspection - NRC Inspection Report 05000327-13-007, 05000328-13-007

ML13098A141
Person / Time
Site:	Sequoyah
Issue date:	04/05/2013
From:	Nease R NRC/RGN-II/DRS/EB1
To:	James Shea Tennessee Valley Authority
References
IR-13-007
Download: ML13098A141 (8)

See also: IR 05000327/2013007

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

245 PEACHTREE CENTER AVENUE NE, SUITE 1200

ATLANTA, GEORGIA 30303-1257

April 5, 2013

Mr. Joseph W. Shea

Vice President, Nuclear Licensing

Tennessee Valley Authority

1101 Market Street, LP 3D-C

Chattanooga, TN 37402-2801

SUBJECT: NOTIFICATION OF SEQUOYAH NUCLEAR PLANT - COMPONENT DESIGN

BASES INSPECTION - NRC INSPECTION REPORT 05000327/2013007,

05000328/2013007

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 (CDBI) at your Sequoyah

Nuclear Plant during the weeks of July 08 - 12, July 22 - 26, and August 5 - 9, 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 April 2, 2013, Mr. Walker confirmed with Mike McBrearty 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 June 17 - 21, 2013

• Onsite weeks: July 08 - 12, July 22 - 26, and August 5 - 9, 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. John Hanna, a Region II Senior Reactor

Analyst, may accompany 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 May 20, 2013. The

J. Shea 2

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 July 1. 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.: 50-327, 50-328

License Nos.: DPR-77, DPR-79

Enclosure:

Information Request for Sequoyah

Nuclear Plant - Component Design Bases

Inspection

cc: (See page 3)

_________________________ xG SUNSI REVIEW COMPLETE G FORM 665 ATTACHED

OFFICE RII:DRS RII:DRS

SIGNATURE RA RA

NAME WALKER NEASE

DATE .4/5/2013 .4/5/2013 4/ /2013 4/ /2013 4/ /2013 4/ /2013 4/ /2013

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

J. Shea 3

cc:

J. T. Carlin

Site Vice President

Sequoyah Nuclear Plant

Tennessee Valley Authority

Electronic Mail Distribution

P. R. Simmons

Plant Manager

Sequoyah Nuclear Plant

Tennessee Valley Authority

Electronic Mail Distribution

J. W. Proffitt

Manager, Site Licensing

Sequoyah Nuclear Plant

Electronic Mail Distribution

C. D. Mackaman

Program Manager, Corporate Licensing

Tennessee Valley Authority

Electronic Mail Distribution

Edward J. Vigluicci

Associate General Counsel, Nuclear

Tennessee Valley Authority

Electronic Mail Distribution

County Mayor

208 Courthouse

625 Georgia Avenue

Chattanooga, TN 37402-2801

Tennessee Department of

Environment & Conservation

Division of Radiological Health

401 Church Street

Nashville, TN 37243

Senior Resident Inspector

U.S. Nuclear Regulatory Commission

Sequoyah Nuclear Plant

2600 Igou Ferry Road

Soddy Daisy, TN 37379-3624

Ann Harris

341 Swing Loop

Rockwood, TN 37854

Letter to Joseph W. Shea from Rebecca L. Nease dated April 5, 2013.

SUBJECT: NOTIFICATION OF SEQUOYAH NUCLEAR PLANT - COMPONENT DESIGN

BASES INSPECTION - NRC INSPECTION REPORT 05000327/2013007,

05000328/2013007

DISTRIBUTION:

RIDSNRRDIRS

PUBLIC

RidsNrrPMSequoyah Resource

INFORMATION REQUEST FOR SEQUOYAH NUCLEAR PLANT

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 April 16,

2010, 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, and 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 April 16, 2010.

8. List and brief description of safety related SSC design modifications implemented since

April 16, 2010.

9. List and brief description of common-cause component failures that have occurred since

April 16, 2010.

10. List and brief description of operability evaluations completed since April 16, 2010.

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

April 16, 2010, 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 April

16, 2010.

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 June 17)

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 Safety-Related systems. (Electronic and 1/2 size - hard copy week of June 17)

27. Index and Legend for PI&Ds.

28. Copy of Operability determination procedure(s).

30. Copies of condition reports associated with findings from previous CDBI.

31. Index (procedure number, titles, and current revision) of station Emergency Operating

Procedures (EOPs), Abnormal Operating Procedures (AOPs), and Annunciator Response

Procedures (ARPs).

32. Copy of any self-assessments performed in preparation for this inspection.

Enclosure

3

33. List of any condition reports generated in preparation for this inspection.

34. Copies of condition reports generated from previous CDBI (2010).

35. Contact information for a person to discuss PRA information prior to the information-

gathering trip. (Name, title, phone number, and e-mail address)

Enclosure