IR 05000390/2012008

Notification of Watts Bar Nuclear Plant, Unit 1, Component Design Bases Inspection - NRC Inspection Report 05000390-12-008

ML112790114
Person / Time
Site:	Watts Bar
Issue date:	10/06/2011
From:	Binoy Desai NRC/RGN-II/DRS/EB1
To:	Krich R Tennessee Valley Authority
References
IR-12-008
Download: ML112790114 (7)

Text

October 06, 2011

SUBJECT:

NOTIFICATION OF WATTS BAR NUCLEAR PLANT, UNIT 1, COMPONENT DESIGN BASES INSPECTION - NRC INSPECTION REPORT 05000390/2012008

Dear Mr. Krich:

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 Watts Bar Nuclear Plant during the weeks of January 30 - February 3, February 13 - 17, and February 27 - March 2, 2012. The inspection team will be led by Shane Sandal, 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 December 6, 2010.

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.

From an email reply on September 29, 2011, Mr. Sandal confirmed with Mr. Riedl 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 January 9 - 13, 2012

Onsite weeks: January 30 - February 3, February 13 - 17, and February 27 -

March 2, 2012

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, will accompany Mr. Sandal 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 January 2, 2012. Contact Mr. Sandal with any questions concerning the requested information. The inspectors will try to

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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 January 23, 2012. Mr. Sandal, will also discuss the following inspection support administrative details: availability of knowledgeable plant engineering and licensing personnel to serve as points of contact during the inspection; method of tracking inspector requests during the inspection; licensee computer access; working space; arrangements for site access; and 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. Sandal at (404) 997-4513 or me at (404) 997-4519.

Sincerely,

/RA/

Binoy B. Desai, Chief

Engineering Branch 1

Division of Reactor Safety Docket Nos.: 50-390 License Nos.: NPF-90

Enclosure: Information Request for Watts Bar Nuclear Plant -

Component Design Bases Inspection

cc w/enc/: (See page 3)

___ML112790114__________________

X SUNSI REVIEW COMPLETE OFFICE RII:DRS RII:DRS

SIGNATURE

/RA/

/RA/

NAME S. SANDAL B. DESAI

DATE 10/ 03 /2011 10/ 06 /2011

E-MAIL COPY?

YES NO YES NO YES NO YES NO YES NO YES NO YES NO

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cc w/encl:

D. E. Grissette Site Vice President Watts Bar Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution

G. A. Boerschig Plant Manager Watts Bar Nuclear Plant, MOB 2R-WBN Tennessee Valley Authority Electronic Mail Distribution

C. J. Riedl Acting Manager, Licensing Watts Bar Nuclear Plant, ADM 1L-WBN Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381

J. W. Shea Manager, Corp. Nuclear Licensing - WBN Tennessee Valley Authority Electronic Mail Distribution

E. J. Vigluicci Assistant General Counsel Tennessee Valley Authority Electronic Mail Distribution

W. D. Crouch Licensing Manager, Unit 2 Watts Bar Nuclear Plant, EQB 1B-WBN Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381

County Mayor P.O. Box 156 Decatur, TN 37322

County Executive 375 Church Street Suite 215 Dayton, TN 37321

Tennessee Department of Environment &

Conservation Division of Radiological Health 401 Church Street Nashville, TN 37243

Senior Resident Inspector U.S. Nuclear Regulatory Commission Watts Bar Nuclear Plant U.S. Nuclear Regulatory Commission 1260 Nuclear Plant Road Spring City, TN 37381-2000

Ann Harris 341 Swing Loop Rockwood, TN 37854

Enclosure INFORMATION REQUEST FOR WATTS BAR 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 1, 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, 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 1, 2010.

8.

List and brief description of safety related SSC design modifications implemented since April 1, 2010.

9.

List and brief description of common-cause component failures that have occurred since April 1, 2010.

Enclosure 10. List and brief description of operability evaluations completed since April 1, 2010.

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 1, 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 1, 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 January 9).

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 ECCS systems (electronic and 1/2 size - hard copy week of January 9).

27. Index and Legend for PI&Ds.

28. Copy of design bases documents for ECCS systems.

29. Copy of Operability determination procedure(s).

30. Copies of condition reports associated with findings from previous CDBI (if applicable).

Enclosure 31. Index (procedure number, titles, and current revision) of station Emergency Operating Procedures (EOPs), Abnormal Operating Procedures (AOPs), and Annunciator Response Procedures (ARPs).

32. Contact information for a person to discuss PRA information prior to the information gathering trip (name, title, phone number, and e-mail address).