IR 05000324/2017008

Us Nuclear Regulatory Commission Evaluation of Changes, Tests, and Experiments and Permanent Plant Modifications Inspection Report 05000325/2017008 and 05000324/2017008

ML17326A491
Person / Time
Site:	Brunswick
Issue date:	11/22/2017
From:	Sandra Walker NRC/RGN-II
To:	William Gideon Duke Energy Progress
References
IR 2017008
Download: ML17326A491 (11)

Text

November 22, 2017

SUBJECT:

BRUNSWICK STEAM ELECTRIC PLANT - U. S. NUCLEAR REGULATORY COMMISSION EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000325/2017008 AND 05000324/2017008

Dear Mr. Gideon:

On October 20, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Brunswick Unit 1 and 2 facilities, and discussed the results of this inspection with you and other 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.: 05000325, 05000324 License Nos.: DPR-71, DPR-62

Enclosure:

Inspection Report 05000325/2017008 and 05000324/2017008 w/Attachment: Supplemental Information

REGION II==

Docket Nos.:

50-325, 50-324

License Nos.:

DPR-71, DPR-62

Report Nos.:

05000325/2017008, 05000324/2017008

Licensee:

Duke Energy Progress, Inc.

Facility:

Brunswick Steam Electric Plant, Units 1 & 2

Location:

8470 River Road, SE Southport, NC 28461

Dates:

October 16 - October 20, 2017

Inspectors:

T. Su, Senior Reactor Inspector (Team Leader)

J. Heath, Reactor Operating Engineer

P. Carman, Construction Inspector D. Strickland, Reactor Inspector (Trainee)

Approved by:

Shakur A. Walker, Chief

Engineering Branch 1

Division of Reactor Safety

SUMMARY

Inspection Report (IR) 05000325/2017008, 05000324/2017008; 10/16/2017 - 10/20/2017;

Brunswick Steam Electric Plant, Units 1 & 2; NRC Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications.

The inspection activities described in this report were performed between October 16, 2017 to October 20, 2017, by three Nuclear Regulatory Commission (NRC) inspectors from Region II and one inspector from NRC Headquarters. No findings were identified. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 4, dated December 2006.

REPORT DETAILS

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R17 Evaluations of Changes, Tests, Experiments and Permanent Plant Modifications

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 20 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 Implementation, 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 20 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 October 20, 2017, the team presented inspection results to Mr. W. Gideon 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

W. Gideon, Site Vice President

T. Sherrill, Reg. Affairs

M. Turkal, Acting Reg. Affairs Manager

L. Grzeck, Manager - Licensing

K. Moser, Plant General Manager

J. Nolin, Engineering General Manager

K. Allen, Director Eng. - Design

N. Smith, I&C Design Manager

G. Grosch, Lead I&C Design Engineer

B. Ginsberg, Hardened Vent SME

NRC Personnel

G. Smith, Senior Resident Inspector, Brunswick

M. Schweig, Resident Inspector, Brunswick

J. Steward, Resident Inspector, Brunswick

LIST OF ITEMS OPENED, CLOSED, DISCUSSED AND UPDATED

Opened and Closed

None.