Letter Sequence Request |
---|
|
|
MONTHYEARML0603800022006-02-0909 February 2006 Letter MC4698, RAI for GL-2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors. Project stage: RAI ML0710701332007-03-14014 March 2007 Task Order No. 004 to Delivery No. DR-03-06-046 Project stage: Other ML0817506352008-07-0101 July 2008 Generic Letter 2004-02, Supplemental Response Project stage: Other LR-N13-0148, Generic Letter 2004-02 In-Vessel Downstream Effects Resolution2013-07-11011 July 2013 Generic Letter 2004-02 In-Vessel Downstream Effects Resolution Project stage: Request ML13219A1102013-07-31031 July 2013 Closure Options for Generic Safety Issue (GSI)-191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance in Resolution of Final Issues Related to Generic Letter (GL) 2004-02... Project stage: Request ML13339A7892013-12-0505 December 2013 12/5/13 e-mail from R.Guzman to B.Meixell GSI-191 Closure Options Due Date Request Project stage: Other ONS-2014-024, Closure Option 1 Response for Generic Safety Issue (GSI)-1 91, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance in Resolution of Final Issues Related to Generic Letter (GL) 2004-02, Potential Impact of Deb2014-02-27027 February 2014 Closure Option 1 Response for Generic Safety Issue (GSI)-1 91, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance in Resolution of Final Issues Related to Generic Letter (GL) 2004-02, Potential Impact of Debris. Project stage: Request ML14113A2212014-04-30030 April 2014 NRC Staff Review of the Documentation Provided by PSEG Nuclear LLC for the Salem Generating Station Units 1 and 2 Concerning Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Project stage: Request ML14219A4822014-08-27027 August 2014 Closeout of Generic Letter, 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML14218A8072014-08-27027 August 2014 NRC Staff Review of the Documentation Provided by Duke Energy for the Oconee Nuclear Station Concerning Resolution of GL 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wat Project stage: Request 2013-07-11
[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] |
Text
DUKE Scott L. Batson ENERGYVice Preside Oconee Nuclear Station Duke Energy ON0IVP 1 7800 Rochester Hwy Seneca, SC 29672 July 31, 2013 o: 864.873.3274 f 864.873.4208 U. S. Nuclear Regulatory Commission Scott.Batson@duke-energy.com ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Duke Energy Carolinas, LLC (Duke Energy)Oconee Nuclear Station (Oconee), Units 1, 2 and 3 Docket Nos. 50-269, 50-270 and 50-287 Closure Options for Generic Safety Issue (GSI)-191, "Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance" in resolution of final Issues related to Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurizer-Water Reactors" By letter dated May 15, 2013, Duke Energy provided an update to the NRC of the on-going efforts at Oconee to close out GSI-1 91. As noted in this letter, Duke Energy evaluated the two methods allowed under Option 1 of SECY-12-0093.
One method was to evaluate against the'Clean Plant Criteria' while the other method was to evaluate Oconee against WCAP-16793-NP, Revision 2 and associated NRC Safety Evaluation (ML 13084A154).
The May 15, 2013 letter also stated: "Duke Energy is currently evaluating both methods and will clarify the method utilized to closeout GSI-1 91 in the follow-up letter noted in Attachment 1." The purpose of this letter is to notify the NRC of Oconee's intent to utilize the WCAP-16793-NP, Revision 2 methodology, as endorsed by the NRC in its Safety Evaluation (ML 13084A1 54) to close GSI-191. This letter is also to provide a schedule for the response back to the NRC on the results of this analysis.
Preliminary results from the LOCADM calculation show that the deposition thickness criteria and peak cladding temperature meet the acceptance criteria established in WCAP-16793-NP, Revision 2.The Safety Evaluation for WCAP-1 6793-NP, Revision 2 includes 14 Limitations and Conditions that must be addressed to meet the requirements to close GSI-191. A review of these Limitations and Conditions has revealed that the size distribution of the fiber debris used in the Oconee emergency sump strainer bypass testing does not meet the fiber size distribution noted in Appendix G of WCAP-1 6793-NP, Revision 2. Oconee's strainer testing occurred in 2006, while the strainer bypass testing requirements were established later. Oconee's emergency sump strainers were designed and manufactured by Control Components Incorporated (CCI).As such, Oconee is evaluating testing conducted by other nuclear sites that utilize CCI emergency sump strainers.
The intent is to evaluate their testing and apply it to Oconee where applicable.
www.duke-energy.com U. S. Nuclear Regulatory Commission July'31, 2013 Page 2 The evaluation of CCI testing by other sites is on-going and there are test cases that align with Oconee's fiber load. Upon completion of the above evaluations, Oconee will document and submit the results of its closure option evaluation to the NRC by December 15, 2013.There are no regulatory commitments made herein.If any questions arise or additional information is needed, please contact Bob Meixell of the Oconee Regulatory Affairs group at (864) 873-3279.I declare under penalty of perjury that the foregoing is true and correct. Executed on July 31, 2013 Very truly yours, Scott L. Batson Vice President Oconee Nuclear Station U. S. Nuclear Regulatory Commission July 31, 2013 Page 3 xc (with Attachment):
Mr. Victor McCree U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Mr. John P. Boska (electronic copy only)Oconee Project Manager, NRR/DORL U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop O-8G9A Rockville, MD 20852-2746 Ed Crowe NRC Senior Resident Inspector Oconee Nuclear Station Ms. Susan E, Jenkins Manager, Infectious and Radioactive Waste Management Bureau of Land and Waste Management Department of Health & Environmental Control 2600 Bull Street, Columbia, SC 29201