IR 05000269/2011013

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

ML111450460
Person / Time
Site:	Oconee
Issue date:	05/24/2011
From:	Hoeg T L NRC/RGN-II/DRS/EB3
To:	Gillespie T P Duke Energy Carolinas
References
IR-11-013
Download: ML111450460 (8)

Text

May 24, 2011

Mr. T. Preston Gillespie, Jr. Site Vice President Duke Energy Carolinas, LLC Oconee Nuclear Station 7800 Rochester Highway Seneca, SC 29672

SUBJECT: ERRATA FOR OCONEE NUCLEAR STATION UNIT 1 - NRC POST-APPROVAL SITE INSPECTION FOR LICENSE RENEWAL, INSPECTION REPORT 05000269/2011013

Dear Mr. Gillespie:

On May 5, 2011, the U.S. Nuclear Regulatory Commission (NRC) issued License Renewal Inspection Report 05000269/2011013 (ML111250604) documenting the results of an inspection conducted in accordance with inspection procedure 71003, "Post-Approval Site Inspection for License Renewal." These errata are issued to clarify the inspection scope description and the summary of findings. Please insert the attached errata where appropriate into License Renewal Inspection Report 05000269/2011013.

We apologize for any inconvenience to you and your staff.

Sincerely,/RA/ Timothy L. Hoeg, Acting Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-269 License Nos. DPR-38

Enclosure:

Errata for NRC Inspection Report 05000269/2011013 cc w/encl: See page 2 DEC 2 cc w/encl: Division of Radiological Health TN Dept. of Environment & Conservation 401 Church Street Nashville, TN 37243-1532

David A. Baxter Vice President, Nuclear Engineering Duke Energy Carolinas, LLC Electronic Mail Distribution

Kent Alter Regulatory Compliance Manager Oconee Nuclear Station Duke Energy Carolinas, LLC 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

Tom D. Ray Engineering Manager Oconee Nuclear Station Duke Energy Carolinas, LLC Electronic Mail Distribution

County Supervisor of Oconee County 415 S. Pine Street Walhalla, SC 29691-2145 W. Lee Cox, III Section Chief Radiation Protection Section N.C. Department of Environmental Commerce & Natural Resources Electronic Mail Distribution

_ML111450460_______ X SUNSI REVIEW COMPLETE OFFICE RII:DRS RII:DRS RII:DRP SIGNATURE RA RA RA NAME JRivera-Ortiz THoeg JBartley DATE 05/ 24 /2011 05/ 24 /2011 5/ 24 /2011 E-MAIL COPY? YES NO YES NO Letter to Preston Gillespie from Timothy L. Hoeg dated May 24, 2011

SUBJECT: ERRATA FOR OCONEE NUCLEAR STATION UNIT 1 - NRC POST-APPROVAL SITE INSPECTION FOR LICENSE RENEWAL, INSPECTION REPORT 05000269/2011013

Distribution w/encl

RIDSNRRDIRS PUBLIC RidsNrrPMOconee Resource

Enclosure ERRATA FOR NRC INSPECTION REPORT 05000269/2011013

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 met. The inspectors also determined that the licensee had administrative controls in place to ensure completion of pending actions scheduled both prior and subsequent to the beginning of the period of extended operation.

The NRC's 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

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 inspection's 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 or in accordance with an established implementation schedule.

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. 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. As described in NUREG-1723, the licensee would conduct these activities during the outage when the heater bundles are scheduled for removal. 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 licensee planned to conduct the VT-3 examination during the outage when the heater bundles are scheduled for removal in order to ensure maximum coverage of the Pressurizer internal clad surfaces. The refueling outage when the heater bundles are scheduled for removal would occur during the PEO.

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 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: