IR 05000259/2017007

Browns Perry Nuclear Plant - U. S. Nuclear Regulatory Commission Evaluation of Changes, Tests, and Experiments and Permanent Plant Modifications Inspection Report 05000259/2017007, 05000260/2017007 and 05000296/2017007

ML18019A241
Person / Time
Site:	Browns Ferry
Issue date:	01/16/2018
From:	Sandra Walker NRC/RGN-II/DRS/EB1
To:	James Shea Tennessee Valley Authority
References
IR 2017007
Download: ML18019A241 (9)

Text

UNITED STATES January 16, 2018

SUBJECT:

BROWNS FERRY NUCLEAR PLANT - U. S. NUCLEAR REGULATORY COMMISSION EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000259/2017007, 05000260/2017007 AND 05000296/2017007

Dear Mr. Shea:

On December 7, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Browns Ferry Unit 1, 2 and 3 facilities, and discussed the results of this inspection with members of your staff. Inspectors documented the results of this inspection in the enclosed inspection report.

The NRC inspectors did not identify any findings or violations of more than minor significance.

In accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response, if any, will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS)

component of NRC's Agencywide Documents Access and Management System (ADAMS).

ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Shakur A. Walker, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 05000259, 05000260, 05000296 License Nos.: DPR-33, DPR-52, DPR-68

Enclosure:

Inspection Report 05000259/2017007, 05000260/2017007 and 05000296/2017007 w/Attachment: Supplemental Information

REGION II==

Docket Nos.: 50-259, 50-260, 50-296 License Nos.: DPR-33, DPR-52, DPR-68 Report Nos.: 05000259/2017007, 05000260/2017007, 05000296/2017007 Licensee: Tennessee Valley Authority (TVA)

Facility: Browns Ferry Nuclear Plant, Units 1, 2, and 3 Location: Corner of Shaw and Nuclear Plant Roads Athens, AL 35611 Dates: December 4 - 7, 2017 Inspectors: R. Patterson, Reactor Inspector (Team Leader)

M. Riley, Reactor Inspector M. Schwieg, Reactor Inspector N. Morgan, Reactor Inspector (Trainee)

Approved by: Shakur A. Walker, Chief Engineering Branch 1 Division of Reactor Safety Enclosure

SUMMARY

Inspection Report (IR) 05000259/2017007, 05000260/2017007, 05000296/2017007; 12/04-08/2017; Browns Ferry Nuclear Plant, Units 1, 2, and 3; NRC Evaluations of Changes,

Tests, and Experiments.

This report covers a one week, on-site inspection by three regional inspectors. No findings or violations were identified. The Nuclear Regulatory Commissions (NRCs) program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 5, dated February 2014.

REPORT DETAILS

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R17 Evaluations of Changes, Tests, and Experiments

a. Inspection Scope

Evaluations of Changes, Tests, and Experiments: The team reviewed six safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR) 50.59, Changes, tests, and experiments, to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The team also reviewed 14 screenings and/or applicability determinations where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The team reviewed these documents to determine if:

• The changes, tests, or experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required;

• The safety issues requiring the changes, tests or experiments were resolved;

• The licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 10 CFR 50.59; and

• The design and licensing basis documentation used to support the change was updated to reflect the change.

The team used, in part, Nuclear Energy Institute (NEI) 96-07, Guidelines for 10 CFR 50.59 Evaluations, Revision 1, to determine acceptability of the completed evaluations and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments, dated November 2000.

This inspection constituted six samples of evaluations and 14 samples of screenings and/or applicability determinations as defined in Inspection Procedure (IP) 71111.17-05.

b. Findings

No findings were identified.

4OA6 Meetings, Including Exit

On December 7, 2017, the team presented inspection results to Mr. DL. Hughes and other members of the licensees staff. The team verified that no proprietary information was retained by the inspectors or documented in this report.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee personnel

D. Hughes, General Manager of Site Operations

R. Filipek, Design Engineering Manager

J. Kent, Director of Plant Support

J. Paul, Site Licensing Manager

J. Garner, Licensing

P. Rescheske, Corporate Licensing

C. Mitchell, Design Engineering

NRC personnel

D. Dumbacher, Senior Resident Inspector, BFN

A. Ruh, Resident Inspector, BFN

S. Walker, Branch Chief, DRS