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| | issue date = 11/29/2012 | | | issue date = 11/29/2012 |
| | title = IR 05000269-12-010; Duke Energy Carolinas, LLC; 11/5-9/2012; Oconee Nuclear Station Unit 1, NRC Post-Approval Site Inspection for License Renewal, Inspection Report | | | title = IR 05000269-12-010; Duke Energy Carolinas, LLC; 11/5-9/2012; Oconee Nuclear Station Unit 1, NRC Post-Approval Site Inspection for License Renewal, Inspection Report |
| | author name = Vias S J | | | author name = Vias S |
| | 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 Corp | | | addressee affiliation = Duke Energy Corp |
| | docket = 05000269 | | | docket = 05000269 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 November 29, 2012 | | {{#Wiki_filter:November 29, 2012 |
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| Mr. T. Preston Gillespie, Jr.
| | ==SUBJECT:== |
| | | OCONEE NUCLEAR STATION UNIT 1 - NRC POST-APPROVAL SITE INSPECTION FOR LICENSE RENEWAL, INSPECTION REPORT 05000269/2012010 |
| Site Vice President Duke Energy Corporation Oconee Nuclear Station 7800 Rochester Highway
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| Seneca, SC 29672-0752 SUBJECT: OCONEE NUCLEAR STATION UNIT 1 - NRC POST-APPROVAL SITE INSPECTION FOR LICENSE RENEWAL, INSPECTION REPORT 05000269/2012010
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| ==Dear Mr. Gillespie,== | | ==Dear Mr. Gillespie,== |
| Jr.: | | Jr.: |
| On November 9, 2012, 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 November 8, 2012, with members of your staff. | | On November 9, 2012, 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 November 8, 2012, with members of your staff. |
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| 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. | | 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. |
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| Steven J. Vias, Chief Engineering Branch 3 Division of Reactor Safety | | Steven J. Vias, Chief Engineering Branch 3 Division of Reactor Safety |
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| Docket Nos. 50-269 License Nos. DPR-38 Enclosure: | | Docket Nos. 50-269 License Nos. DPR-38 |
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| NRC Post Approval Site Inspection For License Renewal, Inspection Report 05000269/2012010 w/Attachment: Supplemental Information cc: (See page 3)
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| _________________________ x G SUNSI REVIEW COMPLETE G FORM 665 ATTACHED OFFICE RII:DRS RII:DRS RII:DRS RII:DRS SIGNATURE RA RA RA RA NAME WILLIAMS RIVERA-ORTIZ VIAS LAKE DATE 11/29/2012 11/29/2012 11/29/2012 11/29/2012 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO T. Preston Gillespie, Jr. 3 cc: Thomas D. Ray
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| Plant Manager Oconee Nuclear Station Duke Energy Corporation Electronic Mail Distribution
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| James A. Kammer
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| Design Engineering Manager Oconee Nuclear Station Duke Energy Corporation Electronic Mail Distribution
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| Robert H. Guy Organizational Effectiveness Manager Oconee Nuclear Station Duke Energy Corporation Electronic Mail Distribution
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| Terry L. Patterson Safety Assurance Manager Duke Energy Corporation Electronic Mail Distribution
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| Kent Alter Regulatory Compliance Manager Oconee Nuclear Station Duke Energy Corporation Electronic Mail Distribution
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| Judy E. Smith Licensing Administrator Oconee Nuclear Station Duke Energy Corporation Electronic Mail Distribution
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| Joseph Michael Frisco, Jr. Vice President, Nuclear Design Engineering
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| General Office Duke Energy Corporation Electronic Mail Distribution M. Christopher Nolan
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| Director - Regulatory Affairs
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| General Office Duke Energy Corporation Electronic Mail Distribution
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| David A. Cummings (acting) Fleet Regulatory Compliance & Licensing
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| Manager General Office Duke Energy Corporation Electronic Mail Distribution
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| Alicia Richardson Licensing Administrative Assistant General Office Duke Energy Corporation Electronic Mail Distribution
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| Lara S. Nichols Deputy General Counsel Duke Energy Corporation Electronic Mail Distribution
| | ===Enclosure:=== |
| | NRC Post Approval Site Inspection For License Renewal, Inspection Report 05000269/2012010 w/Attachment: Supplemental Information |
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| David A. Cummings Associate General Counsel General Office Duke Energy Corporation Electronic Mail Distribution
| | REGION II Docket Nos: 50-269 License Nos: DPR-38 Report No: 05000269/2012010 Licensee: Duke Energy Carolinas, LLC Facility: Oconee Nuclear Station, Unit 1 Location: Seneca, SC 29672 Dates: November 5 - 9, 2012 |
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| Division of Radiological Health TN Dept. of Environment & Conservation 401 Church Street
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| Nashville, TN 37243-1532
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| Sandra Threatt, Manager Nuclear Response and Emergency Environmental Surveillance
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| Bureau of Land and Waste Management Department of Health and Environmental
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| Control 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
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| Charles Brinkman
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| Director Washington Operations Westinghouse Electric Company Electronic Mail Distribution
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| (cc cont'd - See page 4)
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| T. Preston Gillespie, Jr. 4 (cc cont'd) County Supervisor of Oconee County
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| 415 S. Pine Street Walhalla, SC 29691-2145
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| W. Lee Cox, III Section Chief
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| Radiation Protection Section N.C. Department of Environmental Commerce & Natural Resources Electronic Mail Distribution
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| Letter to T. Preston Gillespie, Jr. from Steven J. Vias dated November 29, 2012.
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| SUBJECT: OCONEE NUCLEAR STATION UNIT 1 - NRC POST-APPROVAL SITE INSPECTION FOR LICENSE RENEWAL, INSPECTION REPORT 05000269/2012010
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| Distribution:
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| RIDSNRRDIRS PUBLIC RidsNrrPMOconee Resource Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION II Docket Nos: 50-269 License Nos: DPR-38 Report No: 05000269/2012010 Licensee: Duke Energy Carolinas, LLC Facility: Oconee Nuclear Station, Unit 1 Location: Seneca, SC 29672 Dates: November 5 - 9, 2012
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| Inspectors: Robert Williams Jr., Reactor Inspector Approved by: Steven J. Vias, Chief Engineering Branch 3 Division of Reactor Safety | | Inspectors: Robert Williams Jr., Reactor Inspector Approved by: Steven J. Vias, Chief Engineering Branch 3 Division of Reactor Safety |
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| ===Closed=== | | ===Closed=== |
| : None
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| | None |
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| ===Discussed=== | | ===Discussed=== |
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| ==LIST OF DOCUMENTS REVIEWED== | | ==LIST OF DOCUMENTS REVIEWED== |
| The following is a list of documents reviewed during the inspection.
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| : Inclusion on this list does not imply that the NRC inspectors reviewed the doc uments in their entirety, but rather, that selected sections of the documents were evaluated as part of the overall inspection effort.
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| : Inclusion of a document on this list does not imply NRC acceptance or endorsement of the
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| document or any part of it.
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| ===Calculations===
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| : OSC-10397, Standby Shutdown Facility Diesel Fuel Oil Tank Inspections Program (Commitment 4.32.14), Rev. 0
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| : OSC-10457, Coatings Program (Commitment 4.5), Rev. 0
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| : OSC-10467, Fire Barriers Inspection Program (Commitment 4.18.2), Rev. 0
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| : OSC-8159, SSF Diesel Fuel Oil Storage Tank Inspection, Rev. 1
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| ===Drawings===
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| : 02-8045840D, B&W Internals Components Lower Internals Bolting, Rev. 0
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| ===Other Documents===
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| : 2-9193450-000, Assessment of November 2012 Lower Core Barrel Bolts Inspection Results -
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| : Oconee Unit 1 51-9089393-000, Summary of Structural Analysis to Assess Core Barrel Bolt Inspection Results for B&W Plants 51-9089393-001, Summary of Structural Analysis to Assess Core Barrel Bolt Inspection Results for B&W Plants 51-9112756-002, Technical Justification for Upper and Lower Core Barrel Bolting Volumetric (Ultrasonic) Examinations at Oconee Nuclear Station 51-9141231-001, Technical Justification for Baffle to Former Bolts Volumetric Examination at Oconee Nuclear Station 51-9143222-001, Technical Justification for NDE of RV Internals Flow Distributor Bolts 51-9194156-000, Evaluation of
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| : MRP 227 Loose Parts in the
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| : ONS-1 RCS Certificate of Vision Examination for examiner: N. Schmarje, D. Langenfeld Oconee Unit-1 EOC27 Outage
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| : MRP-227 Ultrasonic Inspection Plan for Babcock & Wilcox (B&W) Reactor Vessel Internals Bolting Oconee Unit-1 EOC27 Outage Reactor Vessel & Internals Visual Examinations Work Order
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| : 02023690-02, U1 RX BLDG Coating Inspection
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| ===Procedures===
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| : 54-ISI-373-000, Remote Underwater Visual Inspection of Babcock & Wilcox (B&W) Reactor Pressure Vessel Internals for Pressurized Water Reactors in Accordance with
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| : MRP-228
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| : Guidelines, Rev. 0
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| : MP-0-A-1000-006, Coating Preparation and Application, Rev. 15
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| : MP-0-A-3005-013, Reactor Building Coating Inspection Procedure, Rev. 4
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| : Problem Identification Program Documents
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| : O-11-10667, During review license renewal inspection data, it was determined that the pipe south of
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| : OLPSW-942 had experienced galvanic corrosion O-12-07152, Regulatory compliance to update UFSAR Chapter 18 to reflect final implementation of license renewal commitment
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| s and programs following entry in to PEO O-12-07793, A review of NRC Regulatory Issue Summary (RIS) 2007-16, Revision 1, "Implementation of the Requirements of 10CFR
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| : 54.37(b) for Holders of Renewed Licenses" Attachment O-12-09334, During a UT and visual inspection several through wall pits were found in the shell of SSF main diesel fuel oil tank O-12-09426,
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| : IP 71003 Inspection-After reviewing
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| : OSC-10467, potential need for revising LRA section 4.16.1.1 O-12-12434, Review of UFSAR change packages
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| }} | | }} |
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Category:Inspection Report
MONTHYEARIR 05000269/20243012024-01-11011 January 2024 Notification of Licensed Operator Initial Examination 05000269/2024301, 05000270/2024301, and 05000287/2024301 ML23331A7982023-12-14014 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report (01R32) IR 05000269/20230032023-11-14014 November 2023 Integrated Inspection Report 05000269/2023003, 05000270/2023003, and 05000287/2023003; and IR 07200040/2023001; and Exercise of Enforcement Discretion IR 05000269/20230052023-08-25025 August 2023 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2 and 3 (Report 05000269/2023005, 05000270/2023005, and 05000287/2023005) IR 05000269/20230112023-08-25025 August 2023 Comprehensive Engineering Team Inspection Report 05000269/2023011 and 05000270/2023011 and 05000287/2023011 IR 05000269/20230022023-07-28028 July 2023 Integrated Inspection Report 05000269/2023002, 05000270/2023002 and 05000287/2023002 IR 05000269/20230102023-07-19019 July 2023 Biennial Problem Identification and Resolution Inspection Report 05000269/2023010 and 05000270/2023010 and 05000287/2023010 and Notice of Violation RA-23-0128, Refuel 32 (O1R32) Steam Generator Tube Inspection Report2023-05-18018 May 2023 Refuel 32 (O1R32) Steam Generator Tube Inspection Report IR 05000269/20230012023-05-12012 May 2023 Integrated Inspection Report 05000269/2023001 and 05000270/2023001 and 05000287/2023001 IR 05000269/20234012023-04-14014 April 2023 Security Baseline Inspection Report 05000269 2023401 and 05000270 2023401 and 05000287 2023401 IR 05000269/20220062023-03-0101 March 2023 Annual Assessment Letter for Oconee Nuclear Nuclear Station, Units 1, 2 and 3 (NRC Inspection Report 05000269/2022006, 05000270/2022006, and 05000287/2022006) ML23037A0772023-02-0606 February 2023 402 Cyber Notification and RFI Letter Final IR 05000269/20220042023-02-0202 February 2023 Integrated Inspection Report 05000269 2022004 and 05000270/2022004 and 05000287/2022004 IR 05000269/20220032022-11-0707 November 2022 Integrated Inspection Station 05000269/2022003 and 05000270/2022003 and 05000287/2022003 IR 05000269/20220112022-09-26026 September 2022 NRC Inspection Report 05000269/2022011 and 05000270/2022011 and 05000287/2022011 IR 05000269/20220052022-08-26026 August 2022 Updated Inspection Plan for Oconee Nuclear Station, Units 1, 2 and 3 - NRC Inspection Report 05000269/2022005, 05000270/2022005, and 05000287/2022005 IR 05000269/20224012022-08-26026 August 2022 Material Control and Accounting Program Inspection Report 05000269/2022401 and 05000270/2022401 and 05000287/2022401 (OUO Removed) IR 05000270/20220022022-07-29029 July 2022 Integrated Inspection Report 05000269/ 2022002 and 05000270/2022002 and 05000287/2022002 IR 05000269/20220102022-06-30030 June 2022 Triennial Fire Protection Inspection Report 05000269/2022010 and 05000270/2022010 and 05000287/2022010 IR 05000269/20224032022-05-0404 May 2022 Security Baseline Target Set Inspection Report 05000269/2022403 and 05000270/2022403 and 05000287/2022403 IR 05000269/20220012022-05-0404 May 2022 Integrated Inspection Report 05000269/2022001, 05000270/2022001 and 05000287/2022001 IR 05000269/20224042022-04-27027 April 2022 Security Baseline Inspection Report 05000269/2022404 and 05000270/2022404 and 05000287/2022404 IR 05000269/20223012022-03-0707 March 2022 Notification of Licensed Operator Initial Examination 05000269/2022301, 05000270/2022301 and 05000287/2022301 IR 05000269/20210062022-03-0202 March 2022 Annual Assessment Letter for Oconee Nuclear Station, Units 1, 2, and 3 (Report 05000269/2021006, 05000270/2021006, and 05000287/2021006) IR 05000269/20220122022-02-24024 February 2022 Safety Conscious Work Environment Issue of Concern Followup Report 05000269/2022012 and 05000270/2022012 and 05000287/2022012 IR 05000269/20224022022-02-16016 February 2022 Security Baseline Inspection Report 05000269/2022402 and 05000270/2022402 and 05000287/2022402 IR 05000269/20210042022-02-14014 February 2022 Integrated Inspection Report 05000269/2021004 and 05000270/2021004 and 05000287/2021004 and Apparent Violation IR 05000269/20210032021-10-28028 October 2021 Integrated Inspection Report 05000269/2021003 and 05000270/2021003 and 05000287/2021003 IR 05000269/20210102021-09-17017 September 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000269/2021010 and 05000270/2021010 and 05000287/2021010 IR 05000269/20210052021-08-26026 August 2021 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2, and 3 (NRC Inspection Report 05000269/2021005, 05000270/2021005, and 05000287/2021005) IR 07200004/20210012021-08-26026 August 2021 Operation of an Independent Spent Fuel Storage Installation Report 07200004/2021001 IR 05000269/20210022021-08-0404 August 2021 Integrated Inspection Report 05000269/2021002 and 05000270/2021002 and 05000287/2021002 IR 05000269/20213012021-07-0606 July 2021 NRC Operator License Examination Report 05000269/2021301, 05000270/2021301, and 05000287/2021301 IR 05000269/20210112021-06-0202 June 2021 Biennial Problem Identification and Resolution Inspection Report 05000269/2021011 and 05000270/2021011 and 05000287/2021011 IR 05000269/20210012021-04-23023 April 2021 Integrated Inspection Report 05000269/2021001 and 05000270/2021001 and 05000287/2021001 IR 05000269/20214012021-04-22022 April 2021 Security Baseline Inspection Report 05000269/2021401, 05000270/2021401 and 05000287/2021401 (U) IR 05000269/20200062021-03-0303 March 2021 Annual Assessment Letter for Oconee Nuclear Station Units 1, 2, & 3 NRC Inspection Report 05000269/2020006, 05000270/2020006, & 05000287/2020006 IR 05000269/20200042021-02-22022 February 2021 Reissue- Oconee Nuclear Station Integrated Inspection Report 05000269/2020004, 05000270/2020004, 05000287/2020004 ML21036A0012021-02-0404 February 2021 Integrated Inspection Report 05000269/2020004 and 05000270/2020004 and 05000287/2020004 IR 05000269/20200102021-01-22022 January 2021 NRC Design Bases Assurance Inspection (Team) Report 05000269/2020010 and 05000270/2020010 and 05000287/2020010 and Notice of Violation IR 05000269/20204012020-11-13013 November 2020 Security Baseline Inspection Report 05000269/2020401 and 05000270/2020401 and 05000287/2020401 IR 05000269/20200032020-11-0404 November 2020 Integrated Inspection Report 05000269/2020003, 05000270/2020003, 05000287/2020003, and 07200004/2020002 IR 05000269/20204202020-10-15015 October 2020 Security Inspection Report 05000269/2020420, 05000270/2020420 and 05000287/2020420 IR 05000269/20200052020-08-17017 August 2020 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2, and 3 (NRC Inspection Report 05000269/2020005, 05000270/2020005, and 05000287/2020005) IR 05000269/20200022020-08-11011 August 2020 Integrated Inspection Report 05000269/2020002 and 05000270/2020002 and 05000287/2020002 ML20192A3212020-07-13013 July 2020 Review of the Fall 2019 Steam Generator Tube Inspection Report IR 05000269/20203012020-06-0909 June 2020 Operator Licensing Operating Test Approval 05000269/2020301, 05000270/2020301 and 05000287/2020301 IR 05000269/20000082020-05-12012 May 2020 Final ASP Analysis - Oconee 1, 2, and 3 (IR 050002692000008) IR 05000287/20020152020-05-12012 May 2020 Final ASP Analysis - Oconee 3 (IR 050002872002015) IR 05000269/20000042020-05-12012 May 2020 Final ASP Analysis - Oconee 1, 2, and 3 (IR 050002692000004) 2024-01-11
[Table view] Category:Letter
MONTHYEARML23304A1422024-02-0101 February 2024 Issuance of Environmental Scoping Summary Report Associated with the U.S. Nuclear Regulatory Commission Staffs Review of the Oconee Nuclear Station, Units 1, 2, & 3, Subsequent License Renewal Application ML24005A2492024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000269/20243012024-01-11011 January 2024 Notification of Licensed Operator Initial Examination 05000269/2024301, 05000270/2024301, and 05000287/2024301 ML23331A7982023-12-14014 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report (01R32) ML23262A9672023-12-13013 December 2023 Alternative to Use RR-22-0174, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section XI, Division 1 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230032023-11-14014 November 2023 Integrated Inspection Report 05000269/2023003, 05000270/2023003, and 05000287/2023003; and IR 07200040/2023001; and Exercise of Enforcement Discretion ML23219A1402023-10-10010 October 2023 Audit Report Proposed Alternative to Use ASME Code Case N-752, Risk Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems XI, Division 1 ML23269A1102023-10-0606 October 2023 Letter to Steven Snider-Revised Schedule for the Environmental Review of the Oconee Nuclear Station, Unit 1, 2, and 3, Subsequent License Renewal Application ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230112023-08-25025 August 2023 Comprehensive Engineering Team Inspection Report 05000269/2023011 and 05000270/2023011 and 05000287/2023011 IR 05000269/20230052023-08-25025 August 2023 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2 and 3 (Report 05000269/2023005, 05000270/2023005, and 05000287/2023005) IR 05000269/20230022023-07-28028 July 2023 Integrated Inspection Report 05000269/2023002, 05000270/2023002 and 05000287/2023002 ML23208A0972023-07-27027 July 2023 Subsequent License Renewal List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected IR 05000269/20230102023-07-19019 July 2023 Biennial Problem Identification and Resolution Inspection Report 05000269/2023010 and 05000270/2023010 and 05000287/2023010 and Notice of Violation ML23178A0682023-07-0303 July 2023 Audit Plan Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 & 3 Systems Section XI, Division 1 ML23132A2392023-06-0101 June 2023 Summary of the April 2023 Remote Environmental Audit Related to the Review of the Subsequent License Renewal Application ML23144A0192023-05-25025 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report (O3R31) IR 05000269/20230012023-05-12012 May 2023 Integrated Inspection Report 05000269/2023001 and 05000270/2023001 and 05000287/2023001 ML23121A0552023-05-0303 May 2023 Acknowledgement of Withdrawal Request to Revise TS 5.5.2 Containment Leakage Rate Testing Program ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23117A0432023-04-20020 April 2023 Framatome, Inc., Part 21 Notification of Existence of a Defect ML23075A0732023-04-0505 April 2023 License Renewal Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application Supplement (EPID Number L-2021-SLE-0002) ML23045A1332023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Achp Letter ML23045A1402023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Shpo Letter ML23045A1432023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - State Tribe Letter ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML23069A1102023-03-10010 March 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML23061A1772023-03-0303 March 2023 Notification of Oconee Nuclear Station Comprehensive Engineering Team Inspection - NRC Inspection Report 05000269/2023011, 05000270/2023011 and 05000287/2023011 IR 05000269/20220062023-03-0101 March 2023 Annual Assessment Letter for Oconee Nuclear Nuclear Station, Units 1, 2 and 3 (NRC Inspection Report 05000269/2022006, 05000270/2022006, and 05000287/2022006) ML23039A1632023-02-0808 February 2023 Requalification Program Inspection ML23037A0772023-02-0606 February 2023 402 Cyber Notification and RFI Letter Final IR 05000269/20220042023-02-0202 February 2023 Integrated Inspection Report 05000269 2022004 and 05000270/2022004 and 05000287/2022004 ML22363A3942023-01-12012 January 2023 Subsequent License Renewal Environmental Report Supplement - Proposed Review Schedule ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22321A0492022-12-0808 December 2022 Issuance of Amendment Nos. 426, 428 and 427, Additional Mode Change Limitations Applicable to the Adoption of TSTF- 359, Revision 9, Increase Flexibility in Mode Restraints ML22329A1042022-11-29029 November 2022 Review of the Fall 2021 Steam Generator Tube Inspection Report ML22321A1582022-11-22022 November 2022 Summary of Conference Call Regarding the Fall 2022 Steam Generator Tube Inspections ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000269/20220032022-11-0707 November 2022 Integrated Inspection Station 05000269/2022003 and 05000270/2022003 and 05000287/2022003 ML22301A0112022-11-0303 November 2022 Request for Withholding Information from Public Disclosure Regarding the SLR Application - September 2, 2022 ML22298A0752022-10-27027 October 2022 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application Duke Energy Letter Dated July 25, 2022 ML22264A0322022-10-20020 October 2022 _Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application - Duke Energy Letter Dated July 8, 2022 IR 05000269/20220112022-09-26026 September 2022 NRC Inspection Report 05000269/2022011 and 05000270/2022011 and 05000287/2022011 ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22222A0072022-09-14014 September 2022 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application ML22231B1362022-09-0101 September 2022 Review of the Draft Environmental Assessment and Findings of No Significant Impact for Catawba Nuclear Station, H.B. Robinson Steam Electric Plant, and Oconee Nuclear Station Independent Spent Fuel Storage Installation Decommissioning Fundi ML22234A0062022-08-30030 August 2022 SLRA - Closed Public Meeting Summary - August 18, 2022 2024-02-01
[Table view] |
Inspection Report - Oconee - 2012010 |
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Text
November 29, 2012
SUBJECT:
OCONEE NUCLEAR STATION UNIT 1 - NRC POST-APPROVAL SITE INSPECTION FOR LICENSE RENEWAL, INSPECTION REPORT 05000269/2012010
Dear Mr. Gillespie,
Jr.:
On November 9, 2012, 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 November 8, 2012, with members of your staff.
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.
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 T. Preston Gillespie, Jr. 2 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/
Steven J. Vias, Chief Engineering Branch 3 Division of Reactor Safety
Docket Nos. 50-269 License Nos. DPR-38
Enclosure:
NRC Post Approval Site Inspection For License Renewal, Inspection Report 05000269/2012010 w/Attachment: Supplemental Information
REGION II Docket Nos: 50-269 License Nos: DPR-38 Report No: 05000269/2012010 Licensee: Duke Energy Carolinas, LLC Facility: Oconee Nuclear Station, Unit 1 Location: Seneca, SC 29672 Dates: November 5 - 9, 2012
Inspectors: Robert Williams Jr., Reactor Inspector Approved by: Steven J. Vias, Chief Engineering Branch 3 Division of Reactor Safety
Enclosure
SUMMARY OF FINDINGS
IR 05000269/2012010; November 5 - 9, 2012; 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, the licensee had administrative controls in place to ensure completion before 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.
A. NRC-Identified
and Self-Revealed Findings None
B. Licensee-Identified Violations
None
REPORT DETAILS
OTHER ACTIVITIES
4OA5 Other Activities: Post-Approval Site Inspection for License Renewal (Phase 1)
.1 Implementation of License Conditions and Commitments, including Aging Management
Programs (AMP)
a. Inspection Scope
The inspectors reviewed a sample of license renewal activities scheduled for the Unit 1 Fall 2012 refueling outage, which was the last outage before the beginning of the period of extended operation (PEO). The inspectors selected this refueling outage because it would present the best opportunity to observe the majority of the one-time inspections associated with license renewal commitments. The objective of this inspection was to maximize observations of the actual implementation of license renewal activities before the beginning of the PEO (February 6, 2013), and 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 NRC Memorandum dated March 6, 2007 (ADAMS Accession Number ML070640041), and (c)meet the future inspection activities described in the Updated Final Safety Analysis Report (UFSAR) supplement submitted pursuant to 10 CFR 54.21(d). The previous Phase 2 implementation of inspection procedure 71003 was completed on August 23, 2012 and is publicly available on ADAMS under accession number ML12277A420. The license renewal application (LRA) for Oconee Nuclear Station, Units 1, 2 and 3 and the corresponding NRC Safety Evaluation Report (SER) documented in NUREG-1723 are publicly available on ADAMS under accession numbers ML003692763 and ML003695154, respectively.
The inspectors reviewed supporting documents; conducted interviews with licensee staff; observed in-process outage activities; and performed visual inspection of structures, systems, and components (SSCs) including those not accessible during power operation. The specific inspection activities conducted for each AMP are also described below. Specific documents reviewed are listed in the report attachment.
ONS Calculation 4.5 - Coatings Program: This AMP specified that, continuing through the period of extended operation, the Coatings Program would ensure that the coatings inside the reactor building to protect the containment liner plate, hatches and penetrations would be effectively managed against loss of material due to corrosion.
The Coatings Program provides controls for selection, procurement, surface preparation, application, and testing of Service Level l coatings. The program also requires visual inspection of accessible coatings inside the Reactor Building, every refueling outage to detect coating degradations, including rusting, blistering, crazing, and peeling.
The inspectors reviewed the licensing basis, program basis documents, implementing procedures, applicable condition reports, and work orders regarding these documents to verify that the program had been implemented as described in the license renewal application. The inspectors verified that the licensee developed procedures and conducted inspections as described in the Program Basis Document and the UFSAR.
The inspectors also verified that the inspections were appropriately scheduled and tracked to meet the required inspection period. Additionally, the inspectors directly observed the implementation of a coatings repair in the U1 reactor building to verify that essential variables such as surface preparation and coating application were performed in accordance with the license renewal commitment.
Based on the review of licensee actions completed at the time of this inspection, the timeliness of those actions, and the administrative controls in place to track pending tasks, the inspectors determined that there was reasonable assurance that the licensee would manage the aging effects associated with the Coatings Program and continue it during the PEO.
ONS Calculation 4.18.1 & 4.18.2 - Fire Protection Program: This AMP specified that the existing Fire Protection Program would be credited to ensure that the licensing basis would continue to be met for the Fire Water System, Fire Hydrants, Fire Barriers and Fire Detection System. Section 18.3.17.8 of the UFSAR supplement for license renewal stated that the Fire Hydrant Flow Tests would be managed by the Fire Protection Program and the Problem Investigation Process. The other portions of the Fire Protection Program were not explicitly identified in the UFSAR supplement, but were all covered within UFSAR Section 9.5.1 under the Fire Protection Program.
During the Phase 2 implementation of inspection procedure 71003, an observation was made that, the Acceptance Criteria or Standard subsection of Section 4.16.1.1 of the LRA, Program Description, stated "For fire barrier penetration seals, no visual indication of cracking, separation from wall, separation of layers of material, holes and ruptures or puncture of seal." The inspectors identified that the implementing procedure for the Fire Barrier inspection utilized a 1/8" crack as an acceptance criterion, contrary to the statement in the Commitment. This issue was entered into the licensee's corrective action program as PIP O-12-09426. At the time of this current inspection, the licensee was implementing the corrective actions detailed in PIP O-12-09426 including developing a license renewal commitment change that would align the acceptance criteria listed in the commitment with those currently in use in the implementing procedure. This would have both the implementing procedure as well as the commitment detail an acceptance criterion of a 1/8" crack.
Based on the review of licensee actions completed at the time of this inspection, the timeliness of those actions, and the administrative controls in place to track pending tasks, the inspectors determined that there was reasonable assurance that the licensee would manage the aging effects associated with the Fire Protection Program and continue it during the PEO.
ONS Calculation 4.32.14 - Standby Shutdown Facility Diesel Fuel Oil Tank Inspection
- The Standby Shutdown Facility (SSF) Diesel Fuel Oil Tank Inspection Program is an aging management program that monitors the loss of tank material due to corrosion. The licensee implemented this program as a preventive maintenance activity that inspects the tank at a frequency of every ten years. An SSF diesel fuel oil tank inspection was performed in August of 2012 to meet a commitment made to the NRC and provide reasonable assurance that the existing inspection program was adequate to manage the aging effects of Microbiologically Induced Corrosion (MIC).
During the Phase 2 implementation of inspection procedure 71003, an observation was made that the SSF diesel fuel oil tank inspection performed in August of 2012 identified 9 locations of through-wall pitting due to MIC at elevations ranging from 790 ft to 786 ft. The corrosion in these areas was removed and the tank was repaired in accordance with requirements of the licensee's repair/replacement program, ASME Section XI, and ASME Section III, which was the construction code of the tank. Due to the close proximity in time of the SSF diesel fuel oil tank inspection and the license renewal Phase 2 inspection, the licensee had not completed the engineering evaluations which were needed for the NRC inspectors to complete their review. This issue was entered into the licensee's corrective action program as PIP O-12-9334. At the time of this current inspection, the licensee was implementing the corrective actions detailed in PIP O-12-09334 including successfully performing post maintenance testing on the repairs made and changing the SSF diesel fuel oil tank inspection frequency from once every ten years to, initially, once every 2 years. The results of the future inspections will be evaluated to determine if the increased inspection frequency is still valid.
Based on the review of licensee actions completed at the time of this inspection, the timeliness of those actions, and the administrative controls in place to track pending tasks, the inspectors determined that there was reasonable assurance that the licensee would manage the aging effects associated with the SSF Diesel Oil Fuel Tank and continue it during the PEO.
ONS Calculation 4.41 And 4.42 - Reactor Vessel Internals Program [NRC Memorandum Commitment No. 11]: On June 16, 2010, Duke sent a letter of intent to adopt "Material Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines, (MRP-227-A)". On November 8, 2010, Duke Energy submitted LAR 2010-06. In that submittal, Duke Energy requested that the NRC review and approve a Reactor Vessel (RV) Internals inspection plan based on "Materials Reliability Program:
Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-Rev.0). The MRP-227 guidance was a proposed industry approach to manage aging of the reactor vessel internal materials and it had been submitted to the NRC for review and approval through the Nuclear Energy Institute in January 2009. The licensee's letter of intent to adopt MRP-227 represented a change to the approach described in the original commitment to manage aging of the reactor vessel internals. Following the Duke's LAR submittal, the NRC issued "NRC Regulatory Issue Summary (RIS) 2011-07 License Renewal Submittal Information for Pressurized Water Reactor Internals Aging Management" dated July 21, 2011, to provide guidance to the utilities pending the issuance of MRP-227-A. On December 16, 2011, the NRC issued Revision 1 of the Safety Evaluation Report to incorporate technical changes required to ensure the final approved version of MRP-2 27 (i.e. MRP-227-A) included all NRC required changes. On June 28, 2012, Duke Energy submitted LAR 2010-06 - Supplement 1 which included a revised inspection plan and a commitment change request. The commitment change request was associated with the anticipated delayed completion dates required by Licensee Action Items 2, 4, 6, and 7 from revision 1 of the SER for MRP-227, Revision 0. At the time of this current inspection the licensee had completed the majority of the items required to implement MRP-227-A; however, the outstanding items (licensee action items 6 and 7) will not be completed prior to entering the PEO, but are currently being tracked by the licensee's corrective action program.
The inspectors reviewed the licensing basis, program basis documents, implementing procedures, applicable condition reports, and work orders regarding these documents to verify that this program was implemented in accordance with the revised commitment as described in the letter submitted to the NRC on June 28, 2012. Additionally, the inspectors observed (either by direct observation or video review) the sample listed below for portions of the visual (VT) and ultrasonic (UT) examinations to verify that essential attributes such as calibration, equipment configuration, and disposition of indications were performed in accordance with the revised license renewal commitment.
- UT examination of the lower core barrel bolting
- UT examination of the flow distributor bolting
- VT examination of the core barrel inside diameter
- VT examination of the SUSI baffle bolting
- VT examination of the lower core barrel bolting
- VT examination of the flow distributor bolting Based on the review of licensee actions completed at the time of this inspection, the timeliness of those actions, and the administrative controls in place to track pending tasks, the inspectors determined that there was reasonable assurance that the licensee would manage the aging effects associated with the Reactor Vessel Internals Program and continue it during the PEO.
b. Findings and Observations
No findings or observations were identified
The review of license renewal commitment changes pursuant to the guidance in NEI 99-04, "Guidelines for Managing NRC Commitment Changes," was completed during the Phase 2 implementation of inspection procedure 71003.
.3 Newly Identified SSCs
The review of newly identified SSCs pursuant 10 CFR 54.37(b) was completed during the Phase 2 implementation of inspection procedure 71003.
.4 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) was completed during the Phase 2 implementation of inspection procedure 71003.
.5 Operating Experience
The review of licensee actions to address recent industry operating experience and its applicability to the existing Aging Management Programs was completed during the Phase 2 implementation of inspection procedure 71003.
4OA6 Management Meetings
.1 Exit Meeting Summary
On November 8, 2012, 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
KEY POINTS OF CONTACT
Licensee
- J. Smith, Licensing Administrator
- H. Galloway, License Renewal Program Owner
- S. Perry, Regulatory Affairs
- E. Swanson, License Renewal Lead
NRC
- S. Vias, Chief, Engineering Branch 3
LIST OF REPORT ITEMS
Opened
None
Closed
None
Discussed
None
LIST OF DOCUMENTS REVIEWED