ML18029A467

Notification of Browns Ferry Nuclear Plant Design Bases Assurance Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000259/2018010, 05000260/2018010, and 05000296/2018010

ML18029A467
Person / Time
Site:	Browns Ferry
Issue date:	01/29/2018
From:	Sykes M D NRC/RGN-II/DRS/EB1
To:	Shea J W Tennessee Valley Authority
References
IR 2018010
Download: ML18029A467 (5)

See also: IR 05000259/2018010

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257

January 29, 2018

Mr. J. W. Shea

Vice President, Nuclear Licensing

Tennessee Valley Authority

1101 Market Street, LP 3D-C

Chattanooga, TN 37402-2801

SUBJECT: NOTIFICATION OF BROWNS FERRY NUCLEAR PLANT DESIGN BASES ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION INSPECTION REPORT 05000259/2018010, 05000260/2018010, AND

05000296/2018010

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 Design Bases Assurance Inspection (DBAI) at your Browns Ferry Nuclear Plant during the weeks of April 30 and May 14, 2018. Mr. Geoffrey Ottenberg, a Senior

Reactor Inspector from the NRC's Region II office, will lead the inspection team. The inspection will be conducted in accordance with Inspection Procedure 71111.21M, "Design Bases

Assurance Inspection (Teams)," dated December 8, 2016 (ADAMS ML16238A320).

The inspection will evaluate the capability of components that have been modified and 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 January 23, 2018, with Mr. Justin Garner, we confirmed

arrangements for an information-gathering site visit and the two-week onsite inspection. The

schedule is as follows:

• Information-gathering visit: Week of April 9, 2018

• Onsite weeks: Weeks of April 30 and May 14, 2018

The purpose of the information-gathering visit is to meet with members of your staff to identify

components that have been modified, risk-significant components and operator actions. Information and documentation needed to support the inspection will also be identified. Mr. Scott Freeman, a Region II Senior Risk Analyst, will support Mr. Ottenberg during the

information-gathering visit to review probabilistic risk assessment data and identify components to be examined during the inspection. Additionally, during the onsite weeks, time will be needed

on the plant-referenced simulator in order to facilitate the development of operator action-based scenarios.

J. Shea 2 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 April 2, 2018. Additional

documents will be requested following the information-gathering visit. The inspectors will try to minimize your administrative burden by specifically identifying only those documents required for inspection preparation. The additional information will be needed in the Region II office by

April 20, 2018, to support the inspection team's preparation week. During the information-

gathering trip, Mr. Ottenberg 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.

This letter, its enclosure, and your response (if any) will be made available for public inspection

and copying at

http://www.nrc.gov/reading-rm/adams.html

and at the NRC Public Document Room in accordance with 10 CFR 2.390, "Public Inspections, Exemptions, Requests for Withholding."

Thank you for your cooperation in this matter. If you have any questions, regarding the

information requested or the inspection, please contact Mr. Ottenberg at 404-997-4658 or

contact me at 404-997-4629.

Sincerely,

/RA/

Marvin D. Sykes, 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:

Notification of Browns Ferry Nuclear Plant

Design Bases Assurance Inspection (Teams)

cc: Distribution via Listserv

____MLXXXXXXXXX__________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS SIGNATURE GKO MDS1 NAME G. Ottenberg M. Sykes DATE 1/29/18 1/29/2018 E-MAIL COPY? YES NO YES NO

Enclosure INFORMATION REQUEST FOR BROWNS FERRY NUCLEAR PLANT DESIGN BASES ASSURANCE INSPECTION (TEAMS)

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. The requested items below, identified with an asterisk (*),

should have a date range from November 1, 2016, until present.

1. *List and brief description of

permanent and field work completed plant modifications including permanent plant changes, design changes, set point changes, procedure changes, equivalency evaluations, suitability analyses, calculations, and commercial grade

dedications. Include an index of systems (system numbers/designators and corresponding

names), the safety classification for each modification, and type of modification.

2. From your most recent probabilistic safety analysis (PSA)

excluding external events and

fires: a. Two risk rankings of components from your site-specific PSA: one sorted by Risk Achievement Worth (RAW), and the other sorted by Birnbaum Importance

b. A list of the top 500 cut-sets

c. A list of the top 500 LERF contributors

3. From your most recent PSA

including external events and fires:

a. Two risk rankings of components from your site-specific PSA: one sorted by RAW, and the other sorted by Birnbaum Importance

b. A list of the top 500 cut-sets

4. Risk ranking of operator actions from your site-specific PSA sorted by RAW and human reliability worksheets for these items

5. List of time-critical operator actions with a brief description of each action

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 motor-operated valve risk-margin rankings, etc.) and associated evaluations or calculations

7. *List and brief description of Root Cause Evaluations performed 8. *List and brief description of common-cause component failures that have occurred

9. List and brief description of equipment currently in degraded or nonconforming status as described in NRC Inspection Manual Chapter 0326, issued December 3, 2015 10. *List and brief description of Operability Determinations and Functionality Assessments

2 11. *List and reason for equipment that has been classified in maintenance rule (a)(1) status

12. *List of equipment on the site's 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) along with dates added or removed from

the issues list

13. List of current "operator work arounds/burdens"

14. Copy of Updated Final Safety Analysis Report

15. Copy of Technical Specification(s)

16. Copy of Technical Specifications Bases

17. Copy of Technical Requirements Manual(s)

18. Copy of the Quality Assurance Program Manual

19. Copy of Corrective Action Program Procedure(s)

20. Copy of Operability Determination Procedure(s)

21. Copy of procedures addressing the following: Modifications, design changes, set point changes, equivalency evaluations or suitability analyses, commercial grade dedications, post-modifications testing, 10 CFR 50.59 screenings and evaluations, and UFSAR updates.

22. List of motor operated valves and air operated valves in the valve program, and their associated design margin and risk ranking

23. Primary AC and DC calculations for safety-related buses

24. One-line diagram of electrical plant (Electronic only)

25. Index and legend for electrical plant one-line diagrams

26. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic)

27. Index and legend for P&IDs

28. Index (procedure number, title, and current revision) of station Emergency Operating Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures

29. Copies of corrective action documents generated from previous CDBI

30. Copy of any self-assessments performed, and corrective action documents generated, in preparation for current DBAI

31. Contact information for a person to discuss PSA information prior to and during the information-gathering trip (Name, title, phone number, and e-mail address)