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| issue date = 05/05/2011
| issue date = 05/05/2011
| title = IR 05000269-11-013, on 04/11/11 - 04/14/11, Oconee Nuclear Station, Unit 1, Post Approval Site Inspection for License Renewal
| title = IR 05000269-11-013, on 04/11/11 - 04/14/11, Oconee Nuclear Station, Unit 1, Post Approval Site Inspection for License Renewal
| author name = Hoeg T L
| author name = Hoeg T
| author affiliation = NRC/RGN-II/DRS/EB3
| author affiliation = NRC/RGN-II/DRS/EB3
| addressee name = Gillespie T P
| addressee name = Gillespie T
| addressee affiliation = Duke Energy Carolinas, LLC
| addressee affiliation = Duke Energy Carolinas, LLC
| docket = 05000269
| docket = 05000269
Line 14: Line 14:
| page count = 10
| page count = 10
}}
}}
See also: [[followed by::IR 05000269/2011013]]
See also: [[see also::IR 05000269/2011013]]


=Text=
=Text=
{{#Wiki_filter: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
{{#Wiki_filter:UNITED STATES
Duke Energy Carolinas, LLC Oconee Nuclear Station 7800 Rochester Highway Seneca, SC 29672 
                            NUCLEAR REGULATORY COMMISSION
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
                                            REGION II
compliance with the Commission's 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.
                        245 PEACHTREE CENTER AVENUE NE, SUITE 1200
  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
                                ATLANTA, GEORGIA 30303-1257
Division of Reactor Safety  Docket Nos.  50-269 License Nos. DPR-38 
                                          May 5, 2011
Enclosure:  NRC Inspection Report 05000269/2011013    w/Attachment: Supplemental Information  cc w/encl:  See page 2
Mr. T. Preston Gillespie, Jr.
DEC 2 cc w/encl: Division of Radiological Health TN Dept. of Environment & Conservation 401 Church Street Nashville, TN  37243-1532 
Site Vice President
David A. Baxter Vice President, Nuclear Engineering Duke Energy Carolinas, LLC Electronic Mail Distribution 
Duke Energy Carolinas, LLC
Kent Alter Regulatory Compliance Manager Oconee Nuclear Station Duke Energy Carolinas, LLC Electronic Mail Distribution  Sandra Threatt, Manager
Oconee Nuclear Station
Nuclear Response and Emergency    Environmental Surveillance Bureau of Land and Waste Management Department of Health and Environmental  Control
7800 Rochester Highway
Electronic Mail Distribution  Scott L. Batson Station Manager Oconee Nuclear Station  
Seneca, SC 29672
Duke Energy Carolinas, LLC Electronic Mail Distribution  Senior Resident Inspector U.S. Nuclear Regulatory Commission
SUBJECT:       OCONEE NUCLEAR STATION UNIT 1 - NRC POST-APPROVAL SITE
Oconee Nuclear Station U.S. Nuclear Regulatory Commission 7812B Rochester Hwy Seneca, SC  29672 
              INSPECTION FOR LICENSE RENEWAL, INSPECTION REPORT
Terry L. Patterson Safety Assurance Manager Duke Energy Carolinas, LLC Electronic Mail Distribution  Charles Brinkman Director
              05000269/2011013
Washington Operations Westinghouse Electric Company, LLC Electronic Mail Distribution 
Dear Mr. Gillespie:
Tom D. Ray Engineering Manager Oconee Nuclear Station Duke Energy Carolinas, LLC Electronic Mail Distribution 
On April 14, 2011, the U.S. Nuclear Regulatory Commission (NRC) completed a Post-Approval
County Supervisor of Oconee County 415 S. Pine Street Walhalla, SC  29691-2145  W. Lee Cox, III
Site Inspection for License Renewal at your Oconee Nuclear Station, Unit 1. The enclosed
Section Chief Radiation Protection Section N.C. Department of Environmental    Commerce & Natural Resources Electronic Mail Distribution
report documents the inspection results, which were discussed on April 14, 2011, with members
  May 5, 2011 Mr. T. Preston Gillespie, Jr. Site Vice President Duke Energy Carolinas, LLC Oconee Nuclear Station 7800 Rochester Highway  
of your staff.
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  
The inspection examined activities conducted under your license as they relate to safety and
compliance with the Commission's 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.  
compliance with the Commissions rules and regulations and with the conditions of your license.
  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  
The inspectors reviewed selected procedures and records, observed activities, and interviewed
Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-269 License Nos. DPR-38  
personnel.
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 
Based on the results of this inspection, no findings were identified.
  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 
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its
Distribution w/encl: RIDSNRRDIRS PUBLIC RidsNrrPMOconee Resource   
enclosure, and your response (if any) will be available electronically for public inspection in the
Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION II Docket Nos: 50-269 License Nos: DPR-38 Report No: 05000269/2011013 Licensee: Duke Energy Carolinas, LLC
NRC Public Document Room or from the Publicly Available Records (PARS) component of
Facility: Oconee Nuclear Station, Unit 1 Location: Seneca, SC 29672  Dates: April 11 - 14, 2011
NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at
  Inspectors: Joel Rivera-Ortiz, Senior Reactor Inspector  Approved by: Tim Hoeg, Chief  Engineering Branch 3 
http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Division of Reactor Safety 
                                              Sincerely,
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. 
                                              /RA/
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. 
                                              Timothy L. Hoeg, Acting Chief
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. 
                                              Engineering Branch 3
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
                                              Division of Reactor Safety
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
Docket Nos. 50-269
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
License Nos. DPR-38
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.     
Enclosure:
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 
NRC Inspection Report 05000269/2011013
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. 
  w/Attachment: Supplemental Information
4 Enclosure 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
cc w/encl:     See page 2
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
5 Enclosure 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 
Attachment  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   


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
}}
}}

Latest revision as of 00:06, 13 November 2019

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 Duke Energy icon.png
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)
v • d • e


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

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