IR 05000424/2014007

IR 05000424-14-007, 05000425-14-007; on 06/09/2014 - 06/27/2014; Vogtle Electric Generating Plant, Units 1 and 2; NRC Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications

ML14205A176
Person / Time
Site:	Vogtle
Issue date:	07/22/2014
From:	Nease R NRC/RGN-II/DRS/EB1
To:	Tynan T Southern Nuclear Operating Co
References
IR-14-007
Download: ML14205A176 (14)

Text

July 22, 2014

SUBJECT:

VOGTLE ELECTRIC GENERATING PLANT - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000424/2014007 AND 05000425/2014007

Dear Mr. Tynan:

On June 27, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Vogtle Electric Generating Plant, Units 1 and 2, and discussed the results of this inspection with Mr. J. Thomas 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 (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 for/

Rebecca L. Nease, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 05000424, 05000425 License Nos.: NPF-68 and NPF-81

Enclosure:

Inspection Report 05000424/2014007 and 05000425/2014007 w/Attachment: Supplementary Information

REGION II==

Docket Nos.:

50-424, 50-425

License Nos.:

NPF-68, NPF-81

Report Nos.:

05000424/2014007, 05000425/2014007

Licensee:

Southern Nuclear Operating Company, Inc. (SNC)

Facility:

Vogtle Electric Generating Plant, Units 1 and 2

Location:

Waynesboro, GA 30830

Dates:

June 9, 2014 - June 27, 2014

Inspectors:

A. Alen, Reactor Inspector (Team Leader)

S. Walker, Senior Reactor Inspector A. Wilson, Construction Projects Inspector

Approved by:

Rebecca L. Nease, Chief

Engineering Branch 1

Division of Reactor Safety

SUMMARY

Inspection Report (IR) 05000424/2014007, 05000425/2014007; 06/09/2014-06/27/2014; Vogtle

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

This report covers a two-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 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 19 screenings 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 19 samples of screenings as defined in Inspection Procedure (IP) 71111.17-04.

Permanent Plant Modifications: The team reviewed 10 permanent plant modifications that had been installed in the plant during the last three years. The modifications reviewed are listed below:

• Design Change Package (DCP) 1060336501, 480-Volt (V) Breakers and 4160/480V Transformer Replacement, Ver. 4.0

• DCP 1081089101, Replacement/Modification of Motor Operators HV8811A/B, Ver. 6.0

• DCP 1102491801, Penetration through Auxiliary Building Roof, Ver. 2.0

• DCP SNC466754, High Efficiency Purge Unit, Ver. 1.0

• DCP 1039002501, Digital Feedwater Control System, Ver. 5.0

• Equivalency Determination (ED) SNC366192, Replace G700 Main Steam Isolation Valve (MSIV) packing with Argo 524, Ver. 1.0

• ED SNC438360, Westinghouse 2D82820G02 5-V Direct Current Power Supply, Ver. 2.0

• ED SNC447263, MSIV Stem Material Change to SA638 Gr 660, Ver. 2.0

• ED SNC491984, Emergency Diesel Generator Jacket Water Gasket Binder Change from Nitrile Butadiene Rubber (NBR) to Styrol Butadiene Rubber (SBR), Ver. 1.0

• ED SNC128991, Reserve Auxiliary Transformer and Generator Step-up Transformer Lighting Arresters, Ver. 1.0

The modifications were selected based upon risk significance, safety significance, and complexity. The team reviewed the modifications selected to determine if:

• the supporting design and licensing basis documentation was updated;

• the changes were in accordance with the specified design requirements;

• the procedures and training plans affected by the modification had been adequately updated;

• the test documentation as required by the applicable test programs had been updated; and

• post-modification testing adequately verified system operability and/or functionality.

The team also used applicable industry standards to evaluate acceptability of the modifications and performed walkdowns of accessible portions of the modifications.

Documents reviewed are listed in the Attachment.

This inspection constituted 10 permanent plant modification samples as defined in IP 71111.17-04.

b. Findings

No findings were identified.

4OA6 Meetings, Including Exit

On June 27, 2014, the team presented inspection results to Mr. J. Thomas 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:

SUPPLEMENTARY INFORMATION

KEY POINTS OF CONTACT

Licensee personnel

L. Mansfield, Fleet Design Director

G. Gunn, Licensing Supervisor

K. Walden, Licensing Engineer

H. Jones, Lead Engineer

J. Wade, Site Design Manager

NRC personnel

M. Cain, Senior Resident Inspector, Vogtle

W. Pursley, Resident Inspector (Acting), Vogtle

LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED

Opened

None

Closed

None

Discussed

None

Updated

None