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MONTHYEARRA-13-1007, 30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model2013-12-16016 December 2013 30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model Project stage: Request ONS-2014-080, License Amendment Request (LAR) to Reduce Allowed Maximum Rated Thermal Power When High Pressure Injection (HPI) Equipment Is Inoperable License Amendment Request No. 2013-032014-06-30030 June 2014 License Amendment Request (LAR) to Reduce Allowed Maximum Rated Thermal Power When High Pressure Injection (HPI) Equipment Is Inoperable License Amendment Request No. 2013-03 Project stage: Request RA-14-0014, Duke Energy Carolinas, LLC (Duke Energy): 10 CFR 50.46 - Annual Report for 2013 for Oconee Nuclear Station, Units 1, 2 and 32014-07-0707 July 2014 Duke Energy Carolinas, LLC (Duke Energy): 10 CFR 50.46 - Annual Report for 2013 for Oconee Nuclear Station, Units 1, 2 and 3 Project stage: Request ML14337A0952014-11-25025 November 2014 Part 21 - Defect in LOCA Analysis for B&W Plants Project stage: Request RA-14-0032, CFR 50.46 - 30-Day Report for Estimated Impacts to Peak Cladding Temperature Due to Fuel Pellet Thermal Conductivity Degradation2014-12-17017 December 2014 CFR 50.46 - 30-Day Report for Estimated Impacts to Peak Cladding Temperature Due to Fuel Pellet Thermal Conductivity Degradation Project stage: Request ML15141A1472015-05-21021 May 2015 Request for Additional Information Regarding LAR to Reduce Allowed Maximum Rated Thermal Power When High Pressure Injection Equipment Is Inoperable LAR No. 2013-031 Project stage: RAI ML15166A0192015-06-0808 June 2015 Response to Request for Additional Information Regarding the License Amendment Request (LAR) to Reduce Allowed Maximum Rated Thermal Power When High Pressure Injection (HPI) Equipment Is Inoperable, LAR No. 2013-03 Project stage: Response to RAI ML15166A3872015-09-24024 September 2015 Issuance of Amendments Regarding Allowed Maximum Rated Thermal Power Project stage: Approval 2014-06-30
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Category:Annual Report
MONTHYEARRA-14-0014, Duke Energy Carolinas, LLC (Duke Energy): 10 CFR 50.46 - Annual Report for 2013 for Oconee Nuclear Station, Units 1, 2 and 32014-07-0707 July 2014 Duke Energy Carolinas, LLC (Duke Energy): 10 CFR 50.46 - Annual Report for 2013 for Oconee Nuclear Station, Units 1, 2 and 3 ONS-2014-067, 2013 Annual Radiological Environmental Operating Report2014-05-15015 May 2014 2013 Annual Radiological Environmental Operating Report ML13190A0042013-07-0101 July 2013 10 CFR 50.59 Annual Report ML0513705792005-05-12012 May 2005 Transmittal of Oconee Nuclear Site, Annual Radiological Environmental Operating Report ML0527004712004-12-31031 December 2004 Annual Report 2004 for Electricities of North Carolina ML0527004682004-12-31031 December 2004 Duke Energy Plants and Independent Spent Fuel Storage Installation, Annual Financial Reports - Summary Annual Report ML0318403822003-06-26026 June 2003 CFR 50.59 Annual Report ML0312203102003-04-24024 April 2003 Site 2002 Annual Radioactive Effluent Release Report ML0309806792003-03-28028 March 2003 Commitment Change Annual Report ML0212104972002-04-16016 April 2002 Annual Effluent Release Report 2014-07-07
[Table view] Category:Letter type:RA
MONTHYEARRA-23-0325, Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX2024-01-0808 January 2024 Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX RA-23-0320, Notification of Deviation from MRP-227, Revision 1-A Baffle-to-Former Bolt Inspection Frequency2023-12-14014 December 2023 Notification of Deviation from MRP-227, Revision 1-A Baffle-to-Former Bolt Inspection Frequency RA-23-0318, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0404 December 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0182, Duke Energy Carolinas, LLC - License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program for a One-Time Extension of the Units 1, 2 and 3 Type a Leak Rate Test Frequency2023-11-16016 November 2023 Duke Energy Carolinas, LLC - License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program for a One-Time Extension of the Units 1, 2 and 3 Type a Leak Rate Test Frequency RA-23-0284, RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0304, Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 32 (Revision 0)2023-11-14014 November 2023 Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 32 (Revision 0) RA-23-0281, Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes2023-11-0101 November 2023 Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes RA-23-0275, Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI)2023-10-12012 October 2023 Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI) RA-23-0268, Transmittal of Sixth 10-Year Inservice Testing Interval Program Plan2023-09-29029 September 2023 Transmittal of Sixth 10-Year Inservice Testing Interval Program Plan RA-23-0234, Update to the Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations for Oconee Nuclear Station (ONS)2023-09-28028 September 2023 Update to the Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations for Oconee Nuclear Station (ONS) RA-23-0225, Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes2023-09-20020 September 2023 Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes RA-23-0228, Registration for Use of General License Spent Fuel Cask Number 1752023-09-14014 September 2023 Registration for Use of General License Spent Fuel Cask Number 175 RA-23-0223, Registration for Use of General License Spent Fuel Cask Numbers 173 and 1742023-08-23023 August 2023 Registration for Use of General License Spent Fuel Cask Numbers 173 and 174 RA-23-0222, On-Shift Staffing Analysis (Ossa), Revision 12023-08-23023 August 2023 On-Shift Staffing Analysis (Ossa), Revision 1 RA-23-0211, Reply to a Notice of Violation (NOV) 05000270/2023010-022023-08-17017 August 2023 Reply to a Notice of Violation (NOV) 05000270/2023010-02 RA-23-0154, Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0136, Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0186, Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 31 (Revision 3)2023-07-18018 July 2023 Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 31 (Revision 3) RA-23-0184, Registration for Use of General License Spent Fuel Cask Numbers 171 and 1722023-07-10010 July 2023 Registration for Use of General License Spent Fuel Cask Numbers 171 and 172 RA-23-0142, Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require2023-07-0707 July 2023 Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require RA-23-0146, Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI)2023-06-20020 June 2023 Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI) RA-23-0135, Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory2023-06-0707 June 2023 Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory RA-23-0041, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-30030 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations RA-23-0128, Refuel 32 (O1R32) Steam Generator Tube Inspection Report2023-05-18018 May 2023 Refuel 32 (O1R32) Steam Generator Tube Inspection Report RA-23-0018, Relief Request (RA-23-0018) to Utilize Code Case N-853 PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material Susceptible to Primary Water Stress Corrosion Cracking Section XI, Division 12023-05-0404 May 2023 Relief Request (RA-23-0018) to Utilize Code Case N-853 PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material Susceptible to Primary Water Stress Corrosion Cracking Section XI, Division 1 RA-23-0111, Withdrawal of License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-04-27027 April 2023 Withdrawal of License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies RA-23-0104, Response to Request for Additional Information (RAI) Regarding Oconee Unit 3, Refuel 31 (O3R31) Steam Generator Tube Inspection Report2023-04-26026 April 2023 Response to Request for Additional Information (RAI) Regarding Oconee Unit 3, Refuel 31 (O3R31) Steam Generator Tube Inspection Report RA-23-0047, Duke Energy Annual Radiological Environmental Operating Report - 20222023-04-26026 April 2023 Duke Energy Annual Radiological Environmental Operating Report - 2022 RA-23-0044, Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.462023-04-26026 April 2023 Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.46 RA-23-0099, Subsequent License Renewal Application Second Annual Amendment to the License Renewal Application2023-04-25025 April 2023 Subsequent License Renewal Application Second Annual Amendment to the License Renewal Application RA-23-0046, Annual Radioactive Effluent Release Report - 20222023-04-24024 April 2023 Annual Radioactive Effluent Release Report - 2022 RA-22-0292, License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-04-0404 April 2023 License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies RA-23-0036, Biennial Decommissioning Financial Assurance Reports2023-03-30030 March 2023 Biennial Decommissioning Financial Assurance Reports RA-23-0040, Onsite Property Insurance Coverage2023-03-30030 March 2023 Onsite Property Insurance Coverage RA-23-0039, 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2023-03-30030 March 2023 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums RA-23-0037, Duke Energy - Decommissioning Funding Plan for Independent Spent Fuel Storage Installations (Isfsis)2023-03-30030 March 2023 Duke Energy - Decommissioning Funding Plan for Independent Spent Fuel Storage Installations (Isfsis) RA-23-0051, Response to Request for Additional Information (RAI) Regarding Proposed Alternative to Use American Society of Mechanical Engineers Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities2023-03-0909 March 2023 Response to Request for Additional Information (RAI) Regarding Proposed Alternative to Use American Society of Mechanical Engineers Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities RA-23-0052, Refuel 32 (O1R32) Inservice Inspection (ISI) Report, Fifth 10-Year ISI Interval2023-02-22022 February 2023 Refuel 32 (O1R32) Inservice Inspection (ISI) Report, Fifth 10-Year ISI Interval RA-22-0257, Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-02-17017 February 2023 Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-23-0001, Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI2023-02-0202 February 2023 Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-22-0256, Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-01-23023 January 2023 Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-22-0335, Submittal of 30-Day Report Per 10CFR26.719(c)(1) - Unsatisfactory Performance of a Health & Human Services Certified Lab2022-12-0505 December 2022 Submittal of 30-Day Report Per 10CFR26.719(c)(1) - Unsatisfactory Performance of a Health & Human Services Certified Lab RA-22-0334, Refuel 31 (O3R31) Steam Generator Tube Inspection Report2022-11-21021 November 2022 Refuel 31 (O3R31) Steam Generator Tube Inspection Report RA-22-0329, Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 1 Cycle 33 (Revision 0 and Revision 1)2022-11-11011 November 2022 Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 1 Cycle 33 (Revision 0 and Revision 1) RA-22-0285, Subsequent License Renewal - Appendix E Environmental Report Supplement 22022-11-0707 November 2022 Subsequent License Renewal - Appendix E Environmental Report Supplement 2 RA-22-0313, Emergency Action Level (EAL) Technical Basis Document, Revision 4, EAL Wallchart, Revision 3 and Alternate TSC and OSC Renovations2022-10-27027 October 2022 Emergency Action Level (EAL) Technical Basis Document, Revision 4, EAL Wallchart, Revision 3 and Alternate TSC and OSC Renovations RA-22-0270, Response to Request for Additional Information Regarding License Amendment Request to Address Technical Specifications Mode Change Limitations2022-10-0707 October 2022 Response to Request for Additional Information Regarding License Amendment Request to Address Technical Specifications Mode Change Limitations RA-22-0192, Subsequent License Renewal Application Response to ONS SLRA Second Round RAI B2.1.7-4a2022-09-0202 September 2022 Subsequent License Renewal Application Response to ONS SLRA Second Round RAI B2.1.7-4a 2024-01-08
[Table view] |
Text
DUK 6wm0 C vkim PradchN Wakk
&operatwn suppad 520 8. Chuwh SOW Ohaftft, NC 28M1g MdkVg Aftsix*
EC07H / P.O. Sax 1008 ChwmoWe, NC 28201-1008
- . 704-8248162 704-M8-4541 fax Serial: RA-14-0014 10 CFR 50.46 July 7, 2014 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Oconee Nuclear Station, Units 1, 2, and 3 Docket Numbers; 0-269,50-270, and 50-287 Renewed Operating License No&. DPR-38, DPR-47, and DPR-55
Subject:
Duke Energy Carolinas, LLC (Duke Energy): 10 CFR 50.46 - Annual Report for 2013 for Oconee Nuclear Station, Units 1, 2, and 3
Reference:
- 1) Letter, G. D. Miller (Duke Energy) to USNRC, 30.Day Report Pursuantto 10 CFR 50.46, Changes to or Errorsin an EvaluationModel, December 16, 2013 (ADAMS Accession No. ML13353A137) 10 CFR 50.46 (a)(3)(H) requires the reporting of changes to or errors in Emergency Core Cooling System (ECCS) evaluation models (EMs). This report covers the time period from January 1, 2013 to December 31,2013 for the Oconee Nuclear Station (ONS). The most recent 10 CFR 50.46 report for ONS (Reference 1) provided the Peak Cladding Temperature (PCT) results of a Large Break Loss of Coolant Accident (LOCA) reanalysis to correct ECCS model errors previously reported to the NRC. Attached are the LOCA PCT margin summary tables for Oconee Units 1, 2, and 3. There are no new regulatory commitments contained in this letter.
Please address any comments or questions regarding this matter to WNlWt K Wwr dt (010) MsueOuke- wgr.um).
(34S Sincerely, Benjamin C.Walr~
Vice PresidentNuclear CorporateGovernance &OperafonsSupport 013 Annual Report of Peak Cladding Temperature L)
/" tC---
U.S. Nuclear Regulatory Commission RA-14-0014 Page 2 xc (with attachment):
V.M.McCree Regional Administrator U.S. Nuclear Regulatory Commission -Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 J. R.Hall NRC Project Manager (ONS) .4f U.S. Nuclear Regulatory Commission One White Flint North, Malt Stop 8G9A 11555 Rockville Pike . .' .. * . ,.,, , ., "
Rockville, MD 20852-2738 Eddy Crowe NRC Senior Resident Inspector Oconee Nucleai Station
U.S. Nuclear Regulatory Commission RA-14-0014 Attachment Page 1 of 3 Attachment Duke Energy Carolinas, LLC*
Oconee Nuclear Station, Unft 1, 2, and 3 10 CFR 60.46 Acceptance Crti for Emergency Core Cooling System for Ught-Water Nucer Power Reactors 2013 Annual Report of Peek Cladding Temperaure Table 1: LOCA Peak Cladding Temperature Margin,11mnary -
Oconee Unts 1,2, and 3
U.S. Nuclear Regulatory Commission RA-14-0014 Attachment Page 2 of 3 Table 1: LOCA Peak Cladding Temperature Margin Summary-Oconee Unite 1, 2, and 3 LSLOCA PnT(F) Commenf.
Evaluation model: RELAPS/MO2-B&W .___ -. ___,..___._,_*
Analysis of record PCT 1852 Reference F Prior 10 CFR 50.46 Changes or Error Corrections (APCT)
- 1. None _. __. _ .....
Current 10 CFR 50.46 Changes or Error Corrections.' Reference G (APCT)
- 1. Transient fuel pellet thermal conductivity
" +2 degradation (considered a change In the application of the evaluation model)
Fial licensing basis PCT -1854, SOLOCA Full Power .10%FP PCI(QF) Comments Evaluation model: RELAPWiMOD2-B&W _. _ _.......
Analysis of record PCT 1598 References A B C
____ysi__ofreordPCT._______,_,_,___ 15(2HPiCase)q.15Wbreak Prior 10 CFR 50.46 Changes or Error Correctior.s References D, E
(&PCT) 0
- 1. ECCS Bypass and Upper Plenum Column Weldment Modeling Current 10 CFR 50.48 Changes or Error Corrections (APCT) 0
- i. None Final licensing basis PCT 15.8 SSLOCA Reduced Power [1l PCT(oF) CommeMts Analysis of record PCT N/A Wil be reported under a separate LAR (References A, B. C)
Prior 10 CFR 50.46 Changes or Error Corrections N/A (APCT)
Current 10 CFR 50.46 Changes or Error Corrections N/A (A*P T) . .. . .. ... . ..... .
Errors (APCT) NIA Final licensing basis PCT N/A Operation Not Justified [21 Notes
- 1. Partial power SBLOCA analysis with one HPI pump out of service, supports 30 day LCO for TS 3.5.2 Condition B. Also supports TS 3.5.2 Condition CI and C2.
- 2. Pending review and approval of separate LAR. Refer to Reference A for additional details.
U.S. Nuclearj'#Igulatory Commission . .
RA-14-0014' Attachment :, ,
Page 3 of 3 References for Table 1:
A) Letter, R. M. Glover (Duke Energy) to USNRC, 30-Day Report Pursuantto 10 CFR50.46, Changes to or Errorsin an EvaluationModel, December 8, 2011 (ADAMS MLI 347A1 93)
B) Letter, B. C. Walirep (Duke Energy) to USNRC, 30-Day andAnnual Report Pursuantto 10 CFR 50.46, Changes to or Errorsin an EvaluationModel, July 5, 2012 (ADAMS ML121910319)
C) Letter, B. C. Waldrep (Duke Energy) to USNRC, 30-Day Report Pursuantto 10 CFR 50.46, Changes to or ErrorsIn an EvaluationModex, December 20, 2012 D) Letter, G. J. St.Clair (AREVA) to S. Thomas (Duke Energy), 10 CFR 50.46 LOCA Report of Two EM ErrorCorrections(AREVA CR 2012-165: ECCS Bypass MathematicalErrorand AREVA CR 2012-757: UpperIPlenum Column Wedkpnt EM Change), Febnuq 23, 2012, AREVA Letter FAB12-120 E) Letter, D. C. Culp (Duke Energy) to USNRC, 30-Day Report Pursuantto 10 CFR 50.46, Changes to or Errorsin an EvaluationModel, March 9,2012 (ADAMS ML12073A354)
F) Letter, G. J. St.Clair (AREVA) to S. Thomas (Duke Energy), 10 CFR 50.46 LOCA Report of an EM ErrorCorrection(A RE VA CR 2013-5610)Related to an Error#ithe fltered Flow Calculationof the FilterBreak Frequency,Noveme 14, 2013, AREVA Letter FABI3-00549 G) AREVA NP Document No. 86-92064-000, TCD TransentAssessment for SWPlants Summary Report,October 21, 2013 (AREVA Proprietary)
....