ML111250604
| 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
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
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
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
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