IR 05000369/2016008

NRC Evaluation of Changes, Tests, and Experiments and Permanent Plant Modifications Inspection Report 05000369/2016008 and 05000370/2016008

ML16305A378
Person / Time
Site:	McGuire, Mcguire
Issue date:	10/25/2016
From:	Bartley J NRC/RGN-II/DRS/EB1
To:	Capps S Duke Energy Carolinas
References
IR 2016008
Download: ML16305A378 (12)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION ber 25, 2016

SUBJECT:

MCGUIRE NUCLEAR STATION - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000369/2016008 AND 05000370/2016008

Dear Mr. Capps:

On September 29, 2016, the U. S. Nuclear Regulatory Commission (NRC) completed an inspection at your McGuire Nuclear Station, Units 1 and 2, and the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspectors did not identify any finding or violation of more than minor significance.

This letter and its enclosure 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.

Sincerely,

/RA/

Jonathan H. Bartley, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 05000369, 05000370 License Nos.: NPF-9, NPF-17

Enclosure:

Inspection Report 05000369/2016008 and 05000370/2016008 w/Attachment:

Supplemental Information

REGION II==

Docket Nos.: 50-369, 50-370 License Nos.: NPF-9, NPF-17 Report Nos.: 05000369/2016008, 05000370/2016008 Licensee: Duke Energy Carolinas, LLC Facility: McGuire Nuclear Station Location: Huntersville, NC 28078 Dates: September 12, 2016, through September 29, 2016 Inspectors: M. Riley, Reactor Inspector (Team Leader)

R. Patterson, Reactor Inspector M. Greenleaf, Reactor Inspector C. Franklin (Trainee)

Approved by: Jonathan H. Bartley, Chief Engineering Branch 1 Division of Reactor Safety Enclosure

SUMMARY

Inspection Report (IR) 05000369/2016008 and 05000370/2016008; September 12 - 29, 2016;

McGuire Nuclear Station, Units 1 & 2; NRC Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications.

This report covers a two-week onsite inspection by four regional reactor inspectors. No findings 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.

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 inspectors reviewed eight 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 inspectors also reviewed 18 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The inspectors 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 inspectors 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 eight evaluation samples and 18 screening and/or applicability determination samples as defined in Inspection Procedure (IP) 71111.17-04.

Permanent Plant Modifications: The inspectors reviewed 11 permanent plant modifications that had been installed during the last three years. The modifications reviewed are listed below:

• EC 098815, 2ETB8, 2ETB12 & 2ETB13 Relay Setting Changes

• EC 101497, Thermal Barrier Hi Flow Set point Increase

• EC 101499, Revise Rotork Actuator Limit Switch MOV 1ND0058A

• EC 101520, Steam Generator Primary Manway Nut Replacement with Hydra-Nut U1

• EC 103396, Design Change Request for FD, Fuel Oil Transfer Pump Motor, 1.0 H.P. AC Motor MNT Replacement 20/40 Exception

• EC 106365, Replace Panelboard 1EKVA

• EC 106409, Replace DC Converters for EDG 1B Speed Switches

• EC 108642, Replace 1NCLT5170 with a Rosemount 1153HD5RB

• EC 112046, Replace Agastat Time Delay Relay 7022AB with Agastat time delay relay E7022AB004

• EC 106112, Replace SSPS Slave Relays with Cutler-Hammer D26MR802A

• Spec-Ngd-Cgd-2006.10-00-0004-002, Mastergear Model MBF 44/11A Gearbox Piece Parts The modifications were selected based upon risk significance, safety significance, and complexity. The inspectors 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 inspectors 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.

b. Findings

No findings were identified.

4OA6 Meetings, Including Exit

On September 29, 2016, the inspectors presented inspection results to Mr. Steven Capps and other members of the licensees staff. The inspectors verified no proprietary information was retained or documented in this report.

ATTACHMENT:

SUPPLEMENTARY INFORMATION

KEY POINTS OF CONTACT

Licensee personnel

S. Capps, Site Vice President

S. Snider, Plant Manager

N. Kunkel, Engineering Manager

J. Robertson, Regulatory Affairs Manager

P. Vu, Regulatory Affairs

B. Richards, Regulatory Affairs

B. Hutchinson, Mechanical Design Principal Engineer

B. Underwood, Mechanical Design Senior Engineer

P. Fuhs, Electrical Design

NRC personnel

F. Ehrhardt, Chief, Projects Branch 5, Division of Reactor Projects

A. Hutto, Senior Resident Inspector, Division of Reactor Projects

R. Cureton, Resident Inspector, Division of Reactor Projects

LIST OF REPORT ITEMS

Opened, Closed, and Discussed

None