|
---|
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] |
Text
June 22, 2020 Mr. J. Ed Burchfield, Jr.
Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672-0752
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 - U. S. NUCLEAR REGULATORY COMMISSION STAFF REVIEW OF BORIC ACID PRECIPITATION EFFECTS WITH RESPECT TO WCAP-16793-NP-A, REVISION 2
Dear Mr. Burchfield:
In September 2004, the U. S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors [PWR], (Agencywide Documents Access and Management System (ADAMS) Accession No. ML042360586) to holders of operating licenses for PWRs. In GL 2004-02, the NRC staff requested that licensees perform an evaluation of their emergency core cooling system (ECCS) and containment spray system (CSS) recirculation functions, considering the potential for debris-laden coolant to be circulated by the ECCS and the CSS after a loss-of-coolant accident (LOCA) or high-energy line break inside containment, and, if appropriate, take additional action to ensure system function. GL 2004-02 required, per Title 10 of the Code of Federal Regulations (10 CFR) Section 50.54(f), that licensees provide the NRC a written response describing the results of their evaluation and any modifications made, or planned, to ensure ECCS and CSS system function during recirculation following a design-basis event, or any alternate action proposed and the basis for its acceptability.
By letter dated August 27, 2014 (ADAMS Accession No. ML14218A807), the NRC documented that the licensee had provided all information required to close GL 2004-02 for Oconee Nuclear Station, Units 1, 2 and 3 (Oconee). Documentation for closure of the in-vessel portion of GL 2004-02 was performed by demonstrating that Oconee met the requirements of topical report (TR) WCAP-16793-NP-A, Revision 2, and the associated NRC staff safety evaluation (SE) (ADAMS Accession No. ML13239A114). In its SE, the NRC staff concluded that plants with relatively low fiber amounts reaching the core could use the TR methodology to show that core cooling would not be adversely affected by debris. However, the SE stated that the potential for debris to change flow patterns or inhibit the mixing of boric acid in the core that might result in earlier boric acid precipitation (BAP) had not been evaluated. This left the question of the effects of debris on the plant licensing basis for BAP open.
The Pressurized Water Reactors Owners Group continued to evaluate the effects of larger amounts of debris on long-term core cooling (LTCC). This work is documented in TR WCAP-17788, Revision 1 (ADAMS Package Accession No. ML20010F181). The NRC staff performed a thorough review of this TR but was unable to conclude that the methodology used for evaluating reactor core debris limits was acceptable for licensing basis calculations.
J. E. Burchfield, Jr. However, the NRC staff found that the TR methodology provided meaningful safety and regulatory insights regarding the treatment of BAP. The staffs technical review of the TR methodology is documented in its technical evaluation report (TER) (ADAMS Accession No. ML19178A252). WCAP-17788, Revision 1, evaluated the potential for debris to affect current BAP analyses and found that BAP timing would not be adversely affected. The NRC performed sensitivity studies during its review of WCAP-17788, Revision 1. These analyses explicitly modeled the physical phenomena that affect the potential for BAP and were conducted for reactor designs considered to be the most limiting with respect to BAP. The analyses found that debris collecting at the core inlet would not adversely affect BAP timing under conditions that conservatively modeled the effects of debris. The NRC staff determined that licensees that demonstrate that their plants fall within specific bounds can maintain their current licensing basis for BAP (Refer to Staff Guidance ADAMS Accession No. ML19228A011), even with debris amounts greater than those approved in WCAP-16793-NP-A, Revision 2.
In its response to GL 2004-02, Oconee demonstrated that it has a very small amount of fiber that may arrive at the core inlet. The NRC staff has determined that this amount of debris will not adversely affect BAP timing and Oconee can maintain its current licensing basis for BAP.
The NRC staff has no further questions related to potential effects of post-accident debris on the reactor vessel. Therefore, the conclusion reached in the NRC letter dated August 27, 2014, indicating that Oconee has adequately responded to the GL remains unchanged.
If you have any questions, please contact me at (301) 415-1009 or via email at Shawn.Williams@nrc.gov.
Sincerely,
/RA/
Shawn A. Williams, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287 cc: Listserv
J. E. Burchfield, Jr.
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 - U. S. NUCLEAR REGULATORY COMMISSION STAFF REVIEW OF BORIC ACID PRECIPITATION EFFECTS WITH RESPECT TO WCAP-16793-NP-A, REVISION 2 DATED JUNE 22, 2020 DISTRIBUTION:
PUBLIC RidsRgn2MailCenter Resource RidsNrrPMOconee Resource RidsACRS_MailCTR Resource RidsNrrLAKGoldstein Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl2-1 Resource SSmith, NRR ARussell, NRR ADAMS Accession No. ML20170A510 *via e-mail OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DSS/STSB/BC NAME SWilliams KGoldstein VCusumano DATE 06/18/2020 06/19/2020 05/20/2020 OFFICE NRR/DORL/LPL2-1/BC NRR/DORL/LPL2 1/PM NAME MMarkley SWilliams DATE 06/22/2020 06/22/2020 OFFICIAL AGENCY RECORD