ML21047A473

Notification of Browns Ferry Nuclear Power Plant Design Bases Assurance Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000259/2021010, 05000260/2021010, and 05000296/2021010

ML21047A473
Person / Time
Site:	Browns Ferry
Issue date:	02/16/2021
From:	James Baptist NRC/RGN-II/DRS/EB1
To:	Jim Barstow Tennessee Valley Authority
References
IR 2021010
Download: ML21047A473 (5)

See also: IR 05000259/2021010

Text

February 16, 2021

Mr. James Barstow

Vice President, Nuclear Regulatory Affairs and Support Services

Tennessee Valley Authority

1101 Market Street, LP 4A-C

Chattanooga, TN 37402-2801

SUBJECT: NOTIFICATION OF BROWNS FERRY NUCLEAR POWER PLANT DESIGN

BASES ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY

COMMISSION INSPECTION REPORT 05000259/2021010, 05000260/2021010,

AND 05000296/2021010

Dear Mr. Barstow:

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 Power Plant during the weeks of May 17 - 21, and June 7 - 11, 2021.

Mr. Marcus Riley, a reactor inspector from the NRCs 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 February 11, 2021, with Mr. Denzel Housley, 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 26 - 30, 2021

• Onsite weeks: Weeks of May 17 - 21, and June 7 - 11, 2021

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. Andy Rosebrook, a Region II Senior Risk Analyst, will support Mr. Riley 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. Barstow 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 Friday, April 16, 2021.

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 Friday, May 7, 2021, to support the inspection teams preparation week. During the

information-gathering trip, Mr. Riley will also discuss the following inspection support

administrative details, as applicable: (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. Riley at 404-997-4888 or contact me

at 404-997-4506.

Sincerely,

/RA/

James Baptist, 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 Power Plant,

Design Bases Assurance Inspection (Teams)

cc: Distribution via Listserv

ML 21047A473

SUNSI X Non-Sensitive X Publicly Available

X

Review Sensitive Non-Publicly Available

OFFICE RII/DRS RII/DRS

NAME M. Riley J. Baptist

DATE 02/12/2021 02/12/2021

INFORMATION REQUEST FOR BROWNS FERRY NUCLEAR POWER 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 January 1, 2018, 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 Operability Determinations and Functionality Assessments

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

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) along with dates added or removed from

the issues list

12. List of current operator work arounds/burdens

13. Copy of Updated Final Safety Analysis Report

14. Copy of Technical Specification(s)

15. Copy of Technical Specifications Bases

16. Copy of Technical Requirements Manual(s)

17. Copy of the Quality Assurance Program Manual

18. Copy of Corrective Action Program Procedure(s)

19. Copy of Operability Determination Procedure(s)

20. List of motor operated valves and air operated valves in the valve program, and their

associated design margin and risk ranking

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

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

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

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

25. Index and legend for P&IDs

26. Index (procedure number, title, and current revision) of station Emergency Operating

Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures

27. Copies of corrective action documents generated from previous CDBI

28. Copy of any self-assessments performed, and corrective action documents generated, in

preparation for current DBAI

29. 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)