ML111250604

IR 05000269-11-013, on 04/11/11 - 04/14/11, Oconee Nuclear Station, Unit 1, Post Approval Site Inspection for License Renewal

ML111250604
Person / Time
Site:	Oconee
Issue date:	05/05/2011
From:	Hoeg T NRC/RGN-II/DRS/EB3
To:	Gillespie T Duke Energy Carolinas
References
IR-11-013
Download: ML111250604 (10)

See also: IR 05000269/2011013

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

245 PEACHTREE CENTER AVENUE NE, SUITE 1200

ATLANTA, GEORGIA 30303-1257

May 5, 2011

Mr. T. Preston Gillespie, Jr.

Site Vice President

Duke Energy Carolinas, LLC

Oconee Nuclear Station

7800 Rochester Highway

Seneca, SC 29672

SUBJECT: OCONEE NUCLEAR STATION UNIT 1 - NRC POST-APPROVAL SITE

INSPECTION FOR LICENSE RENEWAL, INSPECTION REPORT

05000269/2011013

Dear Mr. Gillespie:

On April 14, 2011, the U.S. Nuclear Regulatory Commission (NRC) completed a Post-Approval

Site Inspection for License Renewal at your Oconee Nuclear Station, Unit 1. The enclosed

report documents the inspection results, which were discussed on April 14, 2011, with members

of your staff.

The inspection examined activities conducted under your license as they relate to safety and

compliance with the Commissions rules and regulations and with the conditions of your license.

The inspectors reviewed selected procedures and records, observed activities, and interviewed

personnel.

Based on the results of this inspection, no findings were identified.

In accordance with 10 CFR 2.390 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 document 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/

Timothy L. Hoeg, Acting Chief

Engineering Branch 3

Division of Reactor Safety

Docket Nos. 50-269

License Nos. DPR-38

Enclosure:

NRC Inspection Report 05000269/2011013

w/Attachment: Supplemental Information

cc w/encl: See page 2

DEC 2

cc w/encl: Tom D. Ray

Division of Radiological Health Engineering Manager

TN Dept. of Environment & Conservation Oconee Nuclear Station

401 Church Street Duke Energy Carolinas, LLC

Nashville, TN 37243-1532 Electronic Mail Distribution

David A. Baxter County Supervisor of Oconee County

Vice President, Nuclear Engineering 415 S. Pine Street

Duke Energy Carolinas, LLC Walhalla, SC 29691-2145

Electronic Mail Distribution

W. Lee Cox, III

Kent Alter Section Chief

Regulatory Compliance Manager Radiation Protection Section

Oconee Nuclear Station N.C. Department of Environmental

Duke Energy Carolinas, LLC Commerce & Natural Resources

Electronic Mail Distribution Electronic Mail Distribution

Sandra Threatt, Manager

Nuclear Response and Emergency

Environmental Surveillance

Bureau of Land and Waste Management

Department of Health and Environmental

Control

Electronic Mail Distribution

Scott L. Batson

Station Manager

Oconee Nuclear Station

Duke Energy Carolinas, LLC

Electronic Mail Distribution

Senior Resident Inspector

U.S. Nuclear Regulatory Commission

Oconee Nuclear Station

U.S. Nuclear Regulatory Commission

7812B Rochester Hwy

Seneca, SC 29672

Terry L. Patterson

Safety Assurance Manager

Duke Energy Carolinas, LLC

Electronic Mail Distribution

Charles Brinkman

Director

Washington Operations

Westinghouse Electric Company, LLC

Electronic Mail Distribution

May 5, 2011

Mr. T. Preston Gillespie, Jr.

Site Vice President

Duke Energy Carolinas, LLC

Oconee Nuclear Station

7800 Rochester Highway

Seneca, SC 29672

SUBJECT: OCONEE NUCLEAR STATION UNIT 1 - NRC POST-APPROVAL SITE

INSPECTION FOR LICENSE RENEWAL, INSPECTION REPORT

05000269/2011013

Dear Mr. Gillespie:

On April 14, 2011, the U.S. Nuclear Regulatory Commission (NRC) completed a Post-Approval

Site Inspection for License Renewal at your Oconee Nuclear Station, Unit 1. The enclosed

report documents the inspection results, which were discussed on April 14, 2011, with members

of your staff.

The inspection examined activities conducted under your license as they relate to safety and

compliance with the Commissions rules and regulations and with the conditions of your license.

The inspectors reviewed selected procedures and records, observed activities, and interviewed

personnel.

Based on the results of this inspection, no findings were identified.

In accordance with 10 CFR 2.390 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 document 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/

Timothy L. Hoeg, Acting Chief

Engineering Branch 3

Division of Reactor Safety

Docket Nos. 50-269

License Nos. DPR-38

Enclosure:

NRC Inspection Report 05000269/2011013

w/Attachment: Supplemental Information

cc w/encl: See page 2

X PUBLICLY AVAILABLE G NON-PUBLICLY AVAILABLE G SENSITIVE X NON-SENSITIVE

ADAMS: X Yes ACCESSION NUMBER:__ML111250604______________ X SUNSI REVIEW COMPLETE

OFFICE RII:DRS RII:DRS RII:DRP

SIGNATURE RA RA

NAME JRivera-Ortiz THoeg JBARTLEY

DATE 05/ 5 /2011 05/ 5 /2011 5/5/2011

E-MAIL COPY? YES NO YES NO

OFFICIAL RECORD COPYDOCUMENT NAME: S:\DRS\Eng Branch 3\INSPECTIONS\Working

Documents\INPUTS\Inputs 2011\Oconee U1 IR 2011013 - LR 71003 Phase 1.docx

Letter to Preston Gillespie from Timothy L. Hoeg dated May 5, 2011

SUBJECT: OCONEE NUCLEAR STATION Unit 1 - NRC POST-APPROVAL SITE

INSPECTION FOR LICENSE RENEWAL, INSPECTION REPORT

05000269/2011013

Distribution w/encl:

RIDSNRRDIRS

PUBLIC

RidsNrrPMOconee Resource

U.S. NUCLEAR REGULATORY COMMISSION

REGION II

Docket Nos: 50-269

License Nos: DPR-38

Report No: 05000269/2011013

Licensee: Duke Energy Carolinas, LLC

Facility: Oconee Nuclear Station, Unit 1

Location: Seneca, SC 29672

Dates: April 11 - 14, 2011

Inspectors: Joel Rivera-Ortiz, Senior Reactor Inspector

Approved by: Tim Hoeg, Chief

Engineering Branch 3

Division of Reactor Safety

Enclosure

SUMMARY OF FINDINGS

IR 05000269/2011013; April 11 - 14, 2011; Oconee Nuclear Station Unit 1; Post Approval Site

Inspection for License Renewal

The report covers an inspection conducted by regional inspectors in accordance with NRC

Manual Chapter 2516 and NRC Inspection Procedure 71003.

Based on the sample selected for review, the inspectors determined that commitments, license

conditions, and regulatory requirements associated with the renewed facility operating license

were either being met or, where commitment actions had not been completed, that the licensee

had administrative controls in place to ensure completion before the period of extended

operation.

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.

Enclosure

REPORT DETAILS

4. OTHER ACTIVITIES

4OA5 Other Activities

.1 Post-Approval Site Inspection for License Renewal - IP 71003 (Phase 1)

a. Inspection Scope

(1) Implementation of License Conditions and Commitments, including Aging Management

Programs

The inspectors reviewed a sample of license renewal activities scheduled for the spring

2011 refueling outage, which was the second to last outage prior to the period of

extended operation (PEO). The inspectors conducted this inspection in order to

maximize observations of the actual implementation of license conditions, commitments,

and Aging Management Programs (AMPs) before the PEO (February 6, 2013). The

inspections objective was to verify that the licensee completed the necessary actions to:

(a) comply with the conditions stipulated in the renewed facility operating license; (b)

meet the license renewal commitments described in NUREG-1723, Safety Evaluation

Report (SER) Related to the License Renewal of Oconee Nuclear Station; and (c) meet

the future activities, including AMPs, described in the Updated Final Safety Analysis

Report (UFSAR) supplement submitted pursuant to 10 CFR 54.21(d). A summary of the

license renewal commitments for Oconee Nuclear Station is also available in an NRC

Memorandum dated March 6, 2007 (ML070640041).

Specifically, the inspectors verified that the licensee met the commitments associated

with the one-time Pressurizer examinations described in NUREG-1723 and the UFSAR

supplement. For those Pressurizer examination items that were not completed at the

time of this inspection, the inspectors verified that there was reasonable assurance that

such examination items would be completed prior to the PEO.

The inspection sample for the selected commitment item is described below. Specific

documents reviewed are listed in the report attachment.

Commitment Item 5 - Pressurizer Examinations

Commitment Item 5 in the NRC Memorandum dated March 6, 2007, specified that

Pressurizer examinations would be performed prior to the end of the initial operating

license term. NUREG-1723 and the UFSAR supplement for license renewal described

the planned visual examinations of the internal cladding, spray line, spray head, and

heater bundle penetration welds.

The examination of the Pressurizer internal cladding, spray line, and spray head would

consist of a one-time visual examination (VT-3) in accordance with Section XI of the

American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code.

The examination would cover the internal spray line, the spray head, and the fasteners

that are used to attach the spray line to the internal surface of the Pressurizer. The clad

examination would cover 100 percent of the Pressurizer internal surfaces with emphasis

on the cladding adjacent to the heater bundles based on existing operating experience.

Enclosure

4

The examination of the Pressurizer heater bundle penetration welds would consist of: (a)

a surface exam of 16 peripheral welds on the first removed heater bundle; (b) a VT-3

examination (or equivalent) of the remaining welds of the heater bundle; (c) an

inspection of the heater bundle welds to ASME examination category B-E welds during

the fifth in-service inspection interval; and (d) an inspection of both the heater-sheath-to-

sleeve plate structural weld and the heater-sleeve-to-bundle diaphragm plane structural

weld in Unit 1 only. These examination activities were not scheduled for the spring 2011

refueling outage. However, the licensee scheduled these activities for the outage where

the heater bundles are scheduled for removal as stated in NUREG-1723.

The inspectors reviewed the licensing basis, implementing procedures, engineering

evaluations, personnel qualifications, and non-destructive examination plans to verify

that the Pressurizer examinations performed during the spring 2011 outage were

implemented as stated in the commitment. Additionally, the inspectors observed (either

by direct observation or video review) the sample listed below for portions of the visual

examinations to verify that essential attributes such as calibration, equipment

configuration, and disposition of indications were performed in accordance with the

license renewal commitment.

• VT-3 examination on zone 4, Pressurizer upper dome cladding (Direct observation)

• VT-3 examination of the Pressurizer spray line welds and supports (Direct

observation)

• VT-3 examination of Pressurizer upper head features, nozzle 1-RC-67 (Video)

• VT-3 examination of Pressurizer upper head features from penetration 1-RC-67,

zone 3 (Video)

• VT-3 examination of Pressurizer vessel barrel, elevation 0 inches, zone 1 (Video)

• VT-3 examination of Pressurizer vessel barrel, elevation -6 inches, zone 1 (Video)

• VT-3 examination of Pressurizer vessel barrel, elevation -12 inches, zone 1 (Video)

• VT-3 examination of Pressurizer vessel barrel, elevation -15 inches, zone 1 (Video)

• VT-3 examination of Pressurizer vessel barrel, elevation -18 inches, zone 1 (Video)

• VT-3 examination of Pressurizer vessel barrel, elevation -30 inches, zone 1 (Video)

• VT-3 examination of Pressurizer vessel barrel, elevation -36 inches, zone 1 (Video)

• Calibration for VT-3 examination of Pressurizer vessel barrel zone 1, elevations 0 to -

36 inches (Video)

• Calibration for VT-3 examination of Pressurizer upper head features, nozzle 1-RC-67

(Video)

(2) Review of License Renewal Commitment Changes

The inspectors reviewed license renewal commitment change documents to verify the

licensee followed the guidance in Nuclear Energy Institute (NEI) 99-04, Guidelines for

Managing NRC Commitment Changes, for any change to Commitment Item 5. The

inspectors verified that the licensee properly evaluated, reported, and approved where

necessary, changes to license renewal commitments listed in the UFSAR in accordance

with 10 CFR 50.59. Specifically, the inspectors reviewed the change to the

implementation schedule for the VT-3 examination of the Pressurizer internal clad

surfaces in the area adjacent to the heater bundles.

The inspectors did not identify any examples where commitment changes were not

consistent with the guidance in NEI 99-04. The review of remaining license renewal

Enclosure

5

commitment changes is scheduled to be completed during the Phase 2 implementation

of inspection procedure 71003.

(3) Review of Newly Identified SSCs

This inspection requirement is scheduled to be completed during the Phase 2

implementation of inspection procedure 71003.

(4) Review of the Description of AMPs and Time-Limited Aging Analyses (TLAAs) in the

UFSAR Supplement

The review of the description of AMPs and TLAAs in the UFSAR supplement submitted

pursuant 10 CFR 54.21(d) is scheduled to be completed during the Phase 2

implementation of inspection procedure 71003.

b. Findings and Observations

No findings or observations were identified.

4OA6 Management Meetings

.1 Exit Meeting Summary

On April 14, 2011, the inspectors presented the inspection results to members of the

licensee management staff. The licensee acknowledged the inspection results. The

inspectors confirmed that all proprietary information reviewed during the inspection was

returned to the licensee and that none of the potential report input discussed was

considered proprietary.

ATTACHMENT: SUPPLEMENTAL INFORMATION

Enclosure

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

C. Cruz, Engineering

D. Peltola, Principal Engineer

E. Swanson, Engineering

J. Smith, Licensing

L. Hekking, License Renewal Fleet Program Owner

LIST OF REPORT ITEMS

None

LIST OF DOCUMENTS REVIEWED

03-9155982, Oconee PZR Internals Inspection Operating Instruction, Revision 1

03-9157102, Oconee PZR Internals Inspection Plan, Revision 1

54-ISI-365-02, Visual Inspection of Pressure Vessel Internals, Attachments and Internal

Surfaces, Revision 2

AR 00308431, Determine if a License Amendment Request is Required to Change Section

18.2.5.1 of the UFSAR to Allow an Extension of the Completion Date for a Portion of the

Pressurizer VT-3 Examinations of the Internal Clad Surfaces.

DWG 129252E, Unit 1 Pressurizer Vessel Sub-Assembly, Revision D12

DWG 129254E, Pressurizer Upper Head Assembly and Details, Revision D9

DWG 129266, Pressurizer Vessel Supports and Miscellaneous Details, Revision E6

DWG 24893F, Unit 1 Pressurizer General Arrangement, Revision D16

Nuclear System Directive 214, Regulatory Commitment Management Program, Revision 8

NUREG-1723, Safety Evaluation Report (SER) Related to the License Renewal of Oconee

Nuclear Station

Oconee Nuclear Station Updated Final Safety Analysis Report, Chapter 18, Revision 18

Personnel Qualification Records for VT-3 examiners

SAA Short Form 268, PRA Analysis of ONS Pressurizer Wall Thickness in Corroded Condition

(40 vs. 41.72 years) in Support of a 50.59 Evaluation, 07/22/2010

Safety Document Change Notice 30-9158876-000, Visual Inspection of Pressure Vessel

Internals, Attachments and Internal Surfaces (54-ISI-365-02)

TM/1/A/1165/005, Controlling Procedure for Inspection of Unit 1 Pressurizer Internals by

Vendor, Revision 0

Attachment