IR 05000395/2016008

NRC Evaluation of Changes, Tests, and Experiments and Permanent Plant Modifications Inspection Report 05000395/2016008

ML17017A200
Person / Time
Site:	Summer
Issue date:	01/12/2017
From:	Bartley J NRC/RGN-II/DRS/EB1
To:	Lippard G South Carolina Electric & Gas Co
References
IR 2016008
Download: ML17017A200 (11)

Text

ary 12, 2017

SUBJECT:

VIRGIL C. SUMMER NUCLEAR STATION - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000395/2016008

Dear Mr. Lippard:

On December 9, 2016, the U. S. Nuclear Regulatory Commission (NRC) completed an inspection at your Virgil C. Summer Nuclear Station, Unit 1, 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 No.: 50-395 License No.: NPF-12

Enclosure:

Inspection Report 05000395/2016008 w/Attachment:

Supplemental Information

REGION II==

Docket No.: 50-395 License No.: NPF-12 Report No.: 05000395/2016008 Licensee: South Carolina Electric & Gas (SCE&G) Company Facility: Virgil C. Summer Nuclear Station, Unit 1 Location: P.O. Box 88 Jenkinsville, SC 29065

Dates: November 14, 2016, through December 9, 2016 Inspectors: G. Ottenberg, Senior Reactor Inspector (Team Leader)

P. Braxton, Construction Resident Inspector C. Franklin, Reactor Inspector D. Picirillo, Senior Construction Inspector (Trainee)

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

SUMMARY

Inspection Report (IR) 05000395/2016008; November 14 - December 9, 2016; Virgil C. Summer Nuclear Station, Unit 1; NRC Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications.

This report covers a two-week onsite inspection by two regional reactor inspectors, one resident inspector, and one regional construction inspector. No findings were identified. The Nuclear

Regulatory Commission's (NRC's) program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 6.

REPORT DETAILS

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

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

(71111.17T)

a. Inspection Scope

Evaluations of Changes, Tests, and Experiments: The inspectors reviewed seven 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 14 screenings or applicability determinations where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The samples reviewed are listed in the

. 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 seven evaluation samples and 14 screening and/or applicability determination samples as defined in Inspection Procedure (IP) 71111.17-04.

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

• Commercial Grade Dedication- Purchase Order NU-02SR753804, Wyatt Seal Inc., Viton O-ring

• Commercial Grade Dedication- Purchase Order NU-02SR760205, Shealy Electrical Wholesalers, Fuse

• ECR 50799, Reactor Coolant Pump (RCP) Seal Replacement

• ECR 50893, Engineered Safety Features (ESF) Motor Operated Valves Interlock Logic Change

• ECR 50899, Service Water Traveling Screen Operation after an ESF Signal

• ECR 71587, Setpoint change for instrument number IFB-7273A/B, IFT-7273A/B, IFM-7138, IFM-7158, and IFM-7178 associated with RCPs thermal barrier

• ETBT-72027, Replacement of Gould ITE 222A1175 Relay with ABB 422B1275 Relay 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 December 9, 2016, the inspectors presented inspection results to Mr. G. Lippard and other members of the licensee's staff. The inspectors verified no proprietary information was retained or documented in this report.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee personnel

B. Bennett, Licensing Engineer

G. Lippard, Vice President, Nuclear Operations

W. Martin, Licensing Engineer

M. Moore, Supervisor, Licensing

S. Shealy, Supervisor, Design Engineering

B. Thompson, Manager, Licensing

NRC personnel

A. Masters, Chief, Projects Branch 5, Division of Reactor Projects

S. Ninh, Senior Project Engineer, Division of Reactor Projects

J. Reece, Senior Resident Inspector, Division of Reactor Projects

LIST OF REPORT ITEMS

Opened, Closed, and Discussed

None