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| {{#Wiki_filter:DUKE Michael J. Ainacone 526 South Church Street Charlotte, NC 28202 Mailing Address: Mail Code EC07H / P.O. Box 1006 Charlotte, NC 28201-1006 Office: 980-373-2544 Fax: 704-382-6056 Michae/,Annacone@duke-energy.com 10 CFR 50.4 10 CFR 50.46 July 11, 2013 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Oconee Nuclear Station, Unit 1, 2 and 3 Docket Numbers 50-269, 50-270, and 50-287/Renewed License Numbers DPR-38, DPR-47, and DPR-55 | | {{#Wiki_filter:DUKE Michael J. Ainacone 526 South Church Street Charlotte, NC 28202 Mailing Address: |
| | Mail Code EC07H / P.O. Box 1006 Charlotte, NC 28201-1006 Office: 980-373-2544 Fax: 704-382-6056 Michae/,Annacone@duke-energy.com 10 CFR 50.4 10 CFR 50.46 July 11, 2013 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Oconee Nuclear Station, Unit 1, 2 and 3 Docket Numbers 50-269, 50-270, and 50-287/Renewed License Numbers DPR-38, DPR-47, and DPR-55 |
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| ==Subject:== | | ==Subject:== |
| Duke Energy Carolinas, LLC (Duke Energy): Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model | | Duke Energy Carolinas, LLC (Duke Energy): Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model |
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| Oconee Nuclear Station -Response to NRC RAI regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident Analysis, December 7, 2012. [ADAMS Accession No. ML12348A055] | | Oconee Nuclear Station - Response to NRC RAI regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident Analysis, December 7, 2012. [ADAMS Accession No. ML12348A055] |
| : 3) Letter, G. D. Miller (Duke Energy) to USNRC, | | : 3) Letter, G. D. Miller (Duke Energy) to USNRC, |
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| ==Subject:== | | ==Subject:== |
| Oconee Nuclear Station -Response to NRC RAI regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident Analysis, April 4, 2013. [ADAMS Accession No.ML13102A033] | | Oconee Nuclear Station - Response to NRC RAI regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident Analysis, April 4, 2013. [ADAMS Accession No. |
| 10 CFR 50.46 (a)(3)(ii) requires the reporting of changes to or errors in Emergency Core Cooling (ECCS) evaluation models (EMs). This report covers the time period from January 1, 2012 to December 31, 2012 for the Oconee Nuclear Station (ONS).On February 23, 2012, AREVA notified Duke Energy of two offsetting errors in the ONS ECCS evaluation model. The ECCS bypass calculation model contained the first error, which when corrected, shortened the lower plenum refill time and thus decreased the peak cladding U.S. Nuclear Regulatory Commission July 11,2013 Page 2 temperature (PCT) in both the ruptured and unruptured segments. | | ML13102A033] |
| An 80°F decrease in the ruptured segment PCT and a 40°F decrease in the unruptured segment PCT were assigned to the correction of this error. This error was only applicable to the Large-Break Loss of Coolant Accident (LBLOCA) model. The second error involved enhanced modeling of the upper plenum column weldment over the hot channel which reduced cooling during portions of the blowdown phase and resulted in increases in the ruptured and unruptured segment PCTs. An 80°F increase in the ruptured segment PCT and a 40°F increase in the unruptured segment PCT following a LBLOCA were conservatively assigned to the correction of this error. When correcting for both errors, the net result for a LBLOCA is a 0'F change in both segments. | | 10 CFR 50.46 (a)(3)(ii) requires the reporting of changes to or errors in Emergency Core Cooling (ECCS) evaluation models (EMs). This report covers the time period from January 1, 2012 to December 31, 2012 for the Oconee Nuclear Station (ONS). |
| The impact of the second error on the Small-Break LOCA results was estimated to be 0°F. These errors were reported to the NRC in Reference | | On February 23, 2012, AREVA notified Duke Energy of two offsetting errors in the ONS ECCS evaluation model. The ECCS bypass calculation model contained the first error, which when corrected, shortened the lower plenum refill time and thus decreased the peak cladding |
| : 1. The NRC has issued requests for additional information related to the errors described above. Duke Energy and AREVA have provided responses to these requests in References 2 and 3.There were no other errors in, or changes to, the ONS LOCA analyses during this reporting period. Included in this report are LOCA PCT summary tables for Oconee Units 1, 2, and 3.There are no regulatory commitments contained in this letter.Please address any comments or questions regarding this matter to Paul Guill at (704) 382-4753 (paul.guill@duke-energy.
| | |
| corn).Sincerely, Michael J. Annacone, Vice President | | U.S. Nuclear Regulatory Commission July 11,2013 Page 2 temperature (PCT) in both the ruptured and unruptured segments. An 80°F decrease in the ruptured segment PCT and a 40°F decrease in the unruptured segment PCT were assigned to the correction of this error. This error was only applicable to the Large-Break Loss of Coolant Accident (LBLOCA) model. The second error involved enhanced modeling of the upper plenum column weldment over the hot channel which reduced cooling during portions of the blowdown phase and resulted in increases in the ruptured and unruptured segment PCTs. An 80°F increase in the ruptured segment PCT and a 40°F increase in the unruptured segment PCT following a LBLOCA were conservatively assigned to the correction of this error. When correcting for both errors, the net result for a LBLOCA is a 0'F change in both segments. The impact of the second error on the Small-Break LOCA results was estimated to be 0°F. These errors were reported to the NRC in Reference 1. The NRC has issued requests for additional information related to the errors described above. Duke Energy and AREVA have provided responses to these requests in References 2 and 3. |
| -Organizational Effectiveness | | There were no other errors in, or changes to, the ONS LOCA analyses during this reporting period. Included in this report are LOCA PCT summary tables for Oconee Units 1, 2, and 3. |
| &Regulatory Affairs Attachment Table 1: Mk-B-HTP Full Core Peak Cladding Temperature Summary -Oconee Units 1, 2, and 3 U.S. Nuclear Regulatory Commission July 11,2013 Page 3 xc (with attachment):
| | There are no regulatory commitments contained in this letter. |
| V. M. McCree, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, GA 30303-1257 J. P. Boska, Senior Project Manager (ONS)U. S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8G9A Rockville, MD 20852-2738 E. L. Crowe NRC Senior Resident Inspector Oconee Nuclear Station ATTACHMENT Table 1: Mk-B-HTP Full Core Peak Cladding Temperature Summary Oconee Units 1, 2, and 3 References for Table 1 A) Letter, R. M. Glover (Duke Energy) to USNRC, "30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model", December 8, 2011. [ADAMS MI1 1347A1 93]B) Letter, B. C. Waldrep (Duke Energy) to USNRC, "Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model", July 5, 2012. [ADAMS ML121910319] | | Please address any comments or questions regarding this matter to Paul Guill at (704) 382-4753 (paul.guill@duke-energy.corn). |
| C) Letter, B. C. Waldrep (Duke Energy) to USNRC, "30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model", December 20, 2012.D) Letter, G. J. St.Clair (AREVA) to S. B. Thomas (Duke Energy), "10 CFR 50.46 LOCA Report of Two EM Error Corrections (AREVA CR 20120165: | | Sincerely, Michael J. Annacone, Vice President - Organizational Effectiveness & |
| ECCS Bypass Mathematical Error and AREVA CR 2012-757: | | Regulatory Affairs Attachment Table 1: Mk-B-HTP Full Core Peak Cladding Temperature Summary - Oconee Units 1, 2, and 3 |
| Upper Plenum Column Weldment EM Change)", Dated February 23, 2012, AREVA Letter FAB12-120. | | |
| E) Letter, D. C. Culp (Duke Energy) to USNRC, "30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model", March 9, 2012. [ADAMS ML12073A354] | | U.S. Nuclear Regulatory Commission July 11,2013 Page 3 xc (with attachment): |
| F) Letter, G. D. Miller (Duke Energy) to USNRC, | | V. M. McCree, Region IIAdministrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, GA 30303-1257 J. P. Boska, Senior Project Manager (ONS) |
| | U. S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8G9A Rockville, MD 20852-2738 E. L. Crowe NRC Senior Resident Inspector Oconee Nuclear Station |
| | |
| | ATTACHMENT Table 1: Mk-B-HTP Full Core Peak Cladding Temperature Summary Oconee Units 1, 2, and 3 References for Table 1 A) Letter, R. M. Glover (Duke Energy) to USNRC, "30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model", December 8, 2011. [ADAMS MI1 1347A1 93] |
| | B) Letter, B. C. Waldrep (Duke Energy) to USNRC, "Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model", July 5, 2012. [ADAMS ML121910319] |
| | C) Letter, B. C. Waldrep (Duke Energy) to USNRC, "30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model", December 20, 2012. |
| | D) Letter, G. J. St.Clair (AREVA) to S. B. Thomas (Duke Energy), "10 CFR 50.46 LOCA Report of Two EM Error Corrections (AREVA CR 20120165: ECCS Bypass Mathematical Error and AREVA CR 2012-757: Upper Plenum Column Weldment EM Change)", Dated February 23, 2012, AREVA Letter FAB12-120. |
| | E) Letter, D. C. Culp (Duke Energy) to USNRC, "30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model", March 9, 2012. [ADAMS ML12073A354] |
| | F) Letter, G. D. Miller (Duke Energy) to USNRC, |
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| ==Subject:== | | ==Subject:== |
| Oconee Nuclear Station -Response to NRC RAI regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident Analysis, December 7, 2012. [ADAMS ML12348A055] | | Oconee Nuclear Station - Response to NRC RAI regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident Analysis, December 7, 2012. [ADAMS ML12348A055] |
| G) Letter, G. D. Miller (Duke Energy) to USNRC, | | G) Letter, G. D. Miller (Duke Energy) to USNRC, |
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| ==Subject:== | | ==Subject:== |
| Oconee Nuclear Station -Response to NRC RAI regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident Analysis, April 4, 2013. [ADAMS ML13102A033]Page 1 of 2 Table 1: Mk-B-HTP Full Core Peak Cladding Temperature Summary -Oconee Units 1, 2 & 3 LBLOCA PCT(°F) Comments Evaluation model: RELAP5/MOD2-B&W Analysis of record PCT 1913 References A, B, C Prior errors (APCT)1. None 0 Prior evaluation model changes (APCT)1. None 0 Errors (APCT) References D, E, F, G 1. Error in ECCS Bypass Calculation | | Oconee Nuclear Station - Response to NRC RAI regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident Analysis, April 4, 2013. [ADAMS ML13102A033] |
| -80 Evaluation model changes (APCT) References D, E, F, G 1. Upper Plenum Column Weldment Modeling +80 Absolute value of errors/changes for this report (APCT) 0 Net change in PCT for this report 0 Final PCT 1913 SBLOCA Full Power -100% FP PCT(°F) Comments Evaluation model: RELAP5/MOD2-B&W Analysis of record PCT 1598 References A, B, C (2 HPI Case) 0.15 ft 2 break Prior errors (APCT)1. None 0 Prior evaluation model changes (APCT)1. None 0 Errors (APCT)1. None 0 Evaluation model changes (APCT) References D, E, F, G 1. Upper Plenum Column Weldment Modeling 0 Absolute value of errors/changes for this report (APCT) 0 Net change in PCT for this report 0 Final PCT 1598 SBLOCA Reduced Power- 50% FP [1] PCT(°F) Comments Analysis of record PCT N/A Will be reported under a separate LAR (References A, B, C)Prior errors (APCT) N/A Prior evaluation model changes (APCT) N/A Errors (APCT) N/A Evaluation model changes (APCT) References D, E, F, G 1. Upper Plenum Column Weldment Modeling 0 Absolute value of errors/changes for this report (APCT) N/A Net change in PCT for this report N/A Final PCT N/A Operation Not Justified | | Page 1 of 2 |
| [2]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 Cl and C2.2. Pending review and approval of separate LAR. Refer to Reference A for additional details.Page 2 of 2}} | | |
| | Table 1: Mk-B-HTP Full Core Peak Cladding Temperature Summary - Oconee Units 1, 2 & 3 LBLOCA PCT(°F) Comments Evaluation model: RELAP5/MOD2-B&W Analysis of record PCT 1913 References A, B, C Prior errors (APCT) |
| | : 1. None 0 Prior evaluation model changes (APCT) |
| | : 1. None 0 Errors (APCT) References D, E, F, G |
| | : 1. Error in ECCS Bypass Calculation -80 Evaluation model changes (APCT) References D, E, F, G |
| | : 1. Upper Plenum Column Weldment Modeling +80 Absolute value of errors/changes for this report (APCT) 0 Net change in PCT for this report 0 Final PCT 1913 SBLOCA Full Power -100% FP PCT(°F) Comments Evaluation model: RELAP5/MOD2-B&W Analysis of record PCT 1598 References A, B, C (2 HPI Case) 0.15 ft 2 break Prior errors (APCT) |
| | : 1. None 0 Prior evaluation model changes (APCT) |
| | : 1. None 0 Errors (APCT) |
| | : 1. None 0 Evaluation model changes (APCT) References D, E, F, G |
| | : 1. Upper Plenum Column Weldment Modeling 0 Absolute value of errors/changes for this report (APCT) 0 Net change in PCT for this report 0 Final PCT 1598 SBLOCA Reduced Power- 50% FP [1] PCT(°F) Comments Analysis of record PCT N/A Will be reported under a separate LAR (References A, B, C) |
| | Prior errors (APCT) N/A Prior evaluation model changes (APCT) N/A Errors (APCT) N/A Evaluation model changes (APCT) References D, E, F, G |
| | : 1. Upper Plenum Column Weldment Modeling 0 Absolute value of errors/changes for this report (APCT) N/A Net change in PCT for this report N/A Final PCT N/A Operation Not Justified [2] |
| | 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 Cl and C2. |
| | : 2. Pending review and approval of separate LAR. Refer to Reference A for additional details. |
| | Page 2 of 2}} |
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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
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ML22264A0322022-10-20020 October 2022
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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]
Category:Report
MONTHYEARML23270B8362023-09-26026 September 2023
Code Case N-752 Audit September 26, 2023, E-mail Providing Additional Information Regarding the Use of Owner'S Requirements and Engineering Judgment in Lieu of Code and Standards
ML22269A3882022-09-0707 September 2022
02-Gamma Spectroscopy of Concrete Pucks
RA-20-0280, Submittal of IWB-3640 Analytical Evaluation Performed to Accept an ASME Section XI Code Rejected Sub-Surface Flaw2020-09-14014 September 2020
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ML19242C7282019-08-28028 August 2019
Attachments 5 - 12: Thermal-Hydraulic Models for High Energy Line Break Transient Analysis, Duke Energy/Framatome Affidavits, Regulatory Requirements, Definitions, Time Critical Operator Actions and Feasibility Assessment for New Proposed T
RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019
Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46
ML17031A4312017-01-26026 January 2017
Notification of Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and FLEX Final Integrated Plan
ML16230A2822016-08-17017 August 2016
Duke Power Company Oconee Nuclear Station Unit 2 Integrated Leak Rate Test of the Reactor Containment Building
ML16152A0522016-05-31031 May 2016
ANP-3477NP, Rev. O, MRP-227-A Applicant/Licensee Action Item 6 Analysis
ONS-2016-017, Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2)2016-02-15015 February 2016
Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2)
ML16034A3252015-12-31031 December 2015
Revision 0 to Summary of Methodology Used for Seismic Capacity Evaluation of GMRS Mitigation Components
ML15218A2972015-08-0606 August 2015
Historic Temperature Data Including Record Highs for the Seneca
ML15201A0082015-07-22022 July 2015
Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review
ML15161A4202015-06-15015 June 2015
Review of the Spring 2014 Steam Generator Tube Inservice Inspection Report During Refueling Outage 27
ONS-2015-065, TIA 2014-04, Request for Technical Assistance Regarding the Adequacy of the Station Design and Licensing Bases for the Degraded Voltage Relay2015-05-22022 May 2015
TIA 2014-04, Request for Technical Assistance Regarding the Adequacy of the Station Design and Licensing Bases for the Degraded Voltage Relay
ONS-2015-058, Engineering Report 555, Oconee, Units 1, 2, and 3 - Ul 1569 Impact and Crush Tests on Keowee Underground Trench Power Cables for Duke Energy Carolinas, Llc.2015-03-27027 March 2015
Engineering Report 555, Oconee, Units 1, 2, and 3 - Ul 1569 Impact and Crush Tests on Keowee Underground Trench Power Cables for Duke Energy Carolinas, Llc.
ML16272A2172015-03-0606 March 2015
Revision 1 to Flood Hazard Reevaluation Report on Oconee Nuclear Station, Pp. 1-70, Dated March 6, 2015 (Redacted)
ML16272A2182015-03-0606 March 2015
Revision 1 to Flood Hazard Reevaluation Report on Oconee Nuclear Station, Appendices, Dated March 6, 2015 (Redacted)
ML15072A2172015-02-25025 February 2015
Form OAR-1 Owners Activity Report (CC N-532-4) for Oconee Unit 1, Refueling Outage EOC 28
ONS-2014-161, Submittal of the Expedited Seismic Evaluation Process Report (CEUS Sites)2014-12-19019 December 2014
Submittal of the Expedited Seismic Evaluation Process Report (CEUS Sites)
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
ONS-2014-074, Special Report Per Selected Licensee Commitment 16.9.9 Auxiliary Service Water (Asw) System and Main Steam Atmospheric Dump Valves and Oconee Transition from the Station Asw System to the Protected Service Water System2014-08-15015 August 2014
Special Report Per Selected Licensee Commitment 16.9.9 Auxiliary Service Water (Asw) System and Main Steam Atmospheric Dump Valves and Oconee Transition from the Station Asw System to the Protected Service Water System
ML16272A2162014-04-30030 April 2014
Validation of Hrr Breach Hydrograph for Jocassee Dam, Dated April 30, 2014 (Redacted)
ML15065A3372014-04-23023 April 2014
Response to NRC Request for Additional Information (RAI) Related to the MRP-227-A Applicant/Licensee Action Item #7 Analysis Supporting the Reactor Vessel Internals Inspection Plan Amendment Request (ANP-3267Q1NP (R1))
ML14076A0002014-04-0202 April 2014
Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident
ONS-2014-040, 2013 Annual Commitment Change Report2014-03-31031 March 2014
2013 Annual Commitment Change Report
ONS-2014-046, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3..2014-03-31031 March 2014
Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3..
ML14087A1752014-03-20020 March 2014
ANP-3267Q1NP, Rev. 0, Response to NRC Request for Additional Information (RAI) Related to the MRP-227-A Applicant/Licensee Action Item #7 Analysis Supporting the Reactor Vessel Internals Inspection Plan Amendment Request for Oconee, Units 1
ML13365A2582014-02-10010 February 2014
Interim Staff Evaluation Regarding Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)
ML14028A5122014-02-0404 February 2014
Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Oconee Nuclear Station, Units 1, 2, and 3, TAC Nos.: MF0782, MF0783, and MF0784
ONS-2014-002, Special Report Per Technical Specification 5.6.6, Problem Investigation Process No. O-13-144472014-01-16016 January 2014
Special Report Per Technical Specification 5.6.6, Problem Investigation Process No. O-13-14447
ML13339A3482013-11-30030 November 2013
ANP-3267NP, Revision 0,MRP-227-A Applicant/Licensee Action Item #7 Analysis for the Oconee Nuclear Station Units, Licensing Report
ML13275A3002013-08-31031 August 2013
ANP-3208NP, Rev 1, Confirmation of Stress Relief for ONS-1, ONS-2, ONS-3, and CR-3 Core Support Shield Upper Flange Welds
ML13275A2992013-08-31031 August 2013
ANP-3186NP, Rev 2, ONS License Renewal Scope and MRP-189, Rev. 1 Comparison
ML13196A2482013-07-11011 July 2013
Duke Energy Carolinas, LLC (Duke Energy): Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model
ML13190A0152013-07-0101 July 2013
Aging Management Reviews for Newly Identified Systems, Structures and Components as of December 31, 2012
ML13192A1572013-05-15015 May 2013
Stone & Webster, Inc., Technical Report 1457690202-R-M-00005-0, NTTF 2.3 Seismic Peer Review Supplementary Report, Oconee Nuclear Station Unit 1.
ML13119A0412013-03-31031 March 2013
Attachment 1, ANP-3186NP, Rev. 1, ONS License Renewal Scope and MRP-189, Rev. 1 Comparison.
ML13119A0422013-03-31031 March 2013
Attachment 2, ANP-3208NP, Rev. 0, Confirmation and Stress Relief for ONS-1, ONS-2, ONS-3, and CR-3 Core Support Shield Upper Flange Welds.
ML12347A2522012-11-27027 November 2012
Seismic Walkdown Information Request for Information Pursuant to Title 10 of Code of Federal Regulations Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident 3/12/12
ML16272A2202012-11-27027 November 2012
Enclosure 1: Flood Walkdown Report (NRC 50.54(f) NTTF Recommendation 2.3), Dated November 27, 2012 (Redacted)
ML12347A2532012-11-16016 November 2012
Attachment 6: Nttp 2.3 Seismic Peer Review Report Oconee Nuclear Station Units 1,2 and 3
ML14058A0452012-09-20020 September 2012
History of Oconee Flood Concerns
ML12251A0312012-09-10010 September 2012
Review of the Spring 2011 Steam Generator Tube Inservice Inspections During End of Cycle 26 Refueling Outage
ML12251A0042012-09-0505 September 2012
Unit 3 Cycle 27 Startup Testing Report
ML12187A2152012-03-31031 March 2012
Attachment 1, ANP-2951, Rev. 002, Inspection Plan for the Oconee Nuclear Station, Units 1, 2, and 3, Reactor Vessel Internals, Amp/Application to Implementation MRP-227-A
ML11180A0112011-06-23023 June 2011
Closure of 60-Day Interim Report Notification: Dubose National Energy Services, Inc
ML1108208652011-03-31031 March 2011
Evaluation of 2010 (Cycle 24) Steam Generator (SG) Tube Inspections
ML1100404092010-12-23023 December 2010
Draft, Regarding Review of Root Cause Analysis and Actions Addressing the Underground Pipe Damage to the Condensate Storage Tank Return Line
ML12053A3332010-10-27027 October 2010
Areva Document No. 47-9048125-002, Update of Irradiation Embrittlement in BAW-10008 Part 1 Rev 1, Non-Proprietary
ML1029900642010-10-26026 October 2010
NRC Staff Assessment of Duke Energy Carolinas, Llc. Oconee External Flooding Issue
2023-09-26
[Table view]
Category:Miscellaneous
MONTHYEARML23270B8362023-09-26026 September 2023
Code Case N-752 Audit September 26, 2023, E-mail Providing Additional Information Regarding the Use of Owner'S Requirements and Engineering Judgment in Lieu of Code and Standards
ML19242C7282019-08-28028 August 2019
Attachments 5 - 12: Thermal-Hydraulic Models for High Energy Line Break Transient Analysis, Duke Energy/Framatome Affidavits, Regulatory Requirements, Definitions, Time Critical Operator Actions and Feasibility Assessment for New Proposed T
RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019
Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46
ML17031A4312017-01-26026 January 2017
Notification of Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and FLEX Final Integrated Plan
ML16152A0522016-05-31031 May 2016
ANP-3477NP, Rev. O, MRP-227-A Applicant/Licensee Action Item 6 Analysis
ONS-2016-017, Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2)2016-02-15015 February 2016
Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2)
ML15218A2972015-08-0606 August 2015
Historic Temperature Data Including Record Highs for the Seneca
ML15201A0082015-07-22022 July 2015
Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review
ML15161A4202015-06-15015 June 2015
Review of the Spring 2014 Steam Generator Tube Inservice Inspection Report During Refueling Outage 27
ONS-2015-058, Engineering Report 555, Oconee, Units 1, 2, and 3 - Ul 1569 Impact and Crush Tests on Keowee Underground Trench Power Cables for Duke Energy Carolinas, Llc.2015-03-27027 March 2015
Engineering Report 555, Oconee, Units 1, 2, and 3 - Ul 1569 Impact and Crush Tests on Keowee Underground Trench Power Cables for Duke Energy Carolinas, Llc.
ML15072A2172015-02-25025 February 2015
Form OAR-1 Owners Activity Report (CC N-532-4) for Oconee Unit 1, Refueling Outage EOC 28
ONS-2014-161, Submittal of the Expedited Seismic Evaluation Process Report (CEUS Sites)2014-12-19019 December 2014
Submittal of the Expedited Seismic Evaluation Process Report (CEUS Sites)
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
ONS-2014-074, Special Report Per Selected Licensee Commitment 16.9.9 Auxiliary Service Water (Asw) System and Main Steam Atmospheric Dump Valves and Oconee Transition from the Station Asw System to the Protected Service Water System2014-08-15015 August 2014
Special Report Per Selected Licensee Commitment 16.9.9 Auxiliary Service Water (Asw) System and Main Steam Atmospheric Dump Valves and Oconee Transition from the Station Asw System to the Protected Service Water System
ML14076A0002014-04-0202 April 2014
Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident
ONS-2014-040, 2013 Annual Commitment Change Report2014-03-31031 March 2014
2013 Annual Commitment Change Report
ONS-2014-002, Special Report Per Technical Specification 5.6.6, Problem Investigation Process No. O-13-144472014-01-16016 January 2014
Special Report Per Technical Specification 5.6.6, Problem Investigation Process No. O-13-14447
ML13196A2482013-07-11011 July 2013
Duke Energy Carolinas, LLC (Duke Energy): Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model
ML13190A0152013-07-0101 July 2013
Aging Management Reviews for Newly Identified Systems, Structures and Components as of December 31, 2012
ML14058A0452012-09-20020 September 2012
History of Oconee Flood Concerns
ML12251A0312012-09-10010 September 2012
Review of the Spring 2011 Steam Generator Tube Inservice Inspections During End of Cycle 26 Refueling Outage
ML12187A2152012-03-31031 March 2012
Attachment 1, ANP-2951, Rev. 002, Inspection Plan for the Oconee Nuclear Station, Units 1, 2, and 3, Reactor Vessel Internals, Amp/Application to Implementation MRP-227-A
ML11180A0112011-06-23023 June 2011
Closure of 60-Day Interim Report Notification: Dubose National Energy Services, Inc
ML1108208652011-03-31031 March 2011
Evaluation of 2010 (Cycle 24) Steam Generator (SG) Tube Inspections
ML1100404092010-12-23023 December 2010
Draft, Regarding Review of Root Cause Analysis and Actions Addressing the Underground Pipe Damage to the Condensate Storage Tank Return Line
ML1029104802010-10-20020 October 2010
NRC Assessment of Oconee External Flooding Issue (October 18, 2010)
ML1023001682010-08-16016 August 2010
Units 1 & 2 - Supplement 2 to License Amendment Request for Duke Energy Cyber Security Plan
ML1018201842010-07-0707 July 2010
Evaluation of 2009 (Cycle 24) Steam Generator Tube Inspections
ML1013406842010-05-18018 May 2010
Audit Plan - Technical Adequacy of the Oconee Nuclear Plant'S License Amendment Request for the Transition to 10 CFR 50.48 (C)
ML1019304172010-05-0606 May 2010
Tritium Database Report
ML1012704392010-05-0505 May 2010
Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants
ML1019305452010-02-0808 February 2010
Preliminary Report Oconee Nuclear Station
ML1020105402009-04-20020 April 2009
Letter to Duke Energy from Cline, Site Characterization Report,Groundwater Protection Initiative, Oconee, Appendix D Through Appendix E
ML1020105382009-04-20020 April 2009
Letter to Duke Energy from Cline, Site Characterization Report,Groundwater Protection Initiative, Oconee, Cover Letter Through Appendix C
ML1020105422009-04-20020 April 2009
Letter to Duke Energy from Cline, Site Characterization Report,Groundwater Protection Initiative, Oconee, Appendix E - Continued Through End
ML1020105412009-04-20020 April 2009
Letter to Duke Energy from Cline, Site Characterization Report,Groundwater Protection Initiative, Oconee, Appendix E - Continued
ML0834702462008-12-0909 December 2008
Submittal of Auxiliary Service Water System Outage Report
ML0813502322008-05-12012 May 2008
Summary Ultrasonic Examination Results of Completed Alloy 82/182 Weld Overlays Relief Request 07-ON-004
ML0807101592008-02-29029 February 2008
GL-04-002 Supplemental Response on Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors
ML0735322262007-12-13013 December 2007
Completion of Confirmatory Action Letter Requirements and Summary Ultrasonic Examination Results of Completed Alloy 82/182 Weld Overlays Relief Requests 07-ON-001 and 07-ON-004
ML0706504222007-02-27027 February 2007
Fitness-For-Duty Program Performance Data Reports for Period July 1, 2006 Through December 31, 2006
ML0705300702007-02-21021 February 2007
Emcb Review of the High Energy Line Break Mitigation Strategies for the Oconee Units as Proposed by Duke in a Letter Dated November 30, 2006
ML0702903282006-11-30030 November 2006
Tornado/Helb Mitigation Strategies and Regulatory Commitments
ML0712902832006-11-13013 November 2006
DPO Panel Report-Memo to J. Dyer, NRR, from J. Grobe, Ades/Nrr, Subject: DPO Panel Response to DPO-2006-002
ML0712902512006-10-26026 October 2006
DPO Panel Report-Memo to J. Dyer, NRR, from J. Grobe, Ades/Nrr, Subject: DPO Panel Response to DPO-2006-003
ML0624904272006-08-28028 August 2006
Fitness-For Duty Program Performance Data Reports for Period Covering January 1, 2006 Through June 30, 2006
ML0711501942006-06-0202 June 2006
June 2006 Monthly Report for DPO-2006-002,-003
ML0612404452006-04-12012 April 2006
Future Oconee Tornado Mitigation Strategy
ML0612404672006-03-0909 March 2006
Tornado and High Energy Line Break Events Outside Containment - Supplemental Information
ML0606004492006-02-23023 February 2006
EOC22 Refueling Outage, October-November 2005 Steam Generator Inservice Inspection 3 Month Report
2023-09-26
[Table view] |
Text
DUKE Michael J. Ainacone 526 South Church Street Charlotte, NC 28202 Mailing Address:
Mail Code EC07H / P.O. Box 1006 Charlotte, NC 28201-1006 Office: 980-373-2544 Fax: 704-382-6056 Michae/,Annacone@duke-energy.com 10 CFR 50.4 10 CFR 50.46 July 11, 2013 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Oconee Nuclear Station, Unit 1, 2 and 3 Docket Numbers 50-269, 50-270, and 50-287/Renewed License Numbers DPR-38, DPR-47, and DPR-55
Subject:
Duke Energy Carolinas, LLC (Duke Energy): Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model
Reference:
- 1) Letter, D. C. Culp (Duke Energy) to USNRC,
Subject:
Oconee Nuclear Station Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model, March 9, 2012. [ADAMS Accession No. ML12073A354]
- 2) Letter, G. D. Miller (Duke Energy) to USNRC,
Subject:
Oconee Nuclear Station - Response to NRC RAI regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident Analysis, December 7, 2012. [ADAMS Accession No. ML12348A055]
- 3) Letter, G. D. Miller (Duke Energy) to USNRC,
Subject:
Oconee Nuclear Station - Response to NRC RAI regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident Analysis, April 4, 2013. [ADAMS Accession No.
ML13102A033]
10 CFR 50.46 (a)(3)(ii) requires the reporting of changes to or errors in Emergency Core Cooling (ECCS) evaluation models (EMs). This report covers the time period from January 1, 2012 to December 31, 2012 for the Oconee Nuclear Station (ONS).
On February 23, 2012, AREVA notified Duke Energy of two offsetting errors in the ONS ECCS evaluation model. The ECCS bypass calculation model contained the first error, which when corrected, shortened the lower plenum refill time and thus decreased the peak cladding
U.S. Nuclear Regulatory Commission July 11,2013 Page 2 temperature (PCT) in both the ruptured and unruptured segments. An 80°F decrease in the ruptured segment PCT and a 40°F decrease in the unruptured segment PCT were assigned to the correction of this error. This error was only applicable to the Large-Break Loss of Coolant Accident (LBLOCA) model. The second error involved enhanced modeling of the upper plenum column weldment over the hot channel which reduced cooling during portions of the blowdown phase and resulted in increases in the ruptured and unruptured segment PCTs. An 80°F increase in the ruptured segment PCT and a 40°F increase in the unruptured segment PCT following a LBLOCA were conservatively assigned to the correction of this error. When correcting for both errors, the net result for a LBLOCA is a 0'F change in both segments. The impact of the second error on the Small-Break LOCA results was estimated to be 0°F. These errors were reported to the NRC in Reference 1. The NRC has issued requests for additional information related to the errors described above. Duke Energy and AREVA have provided responses to these requests in References 2 and 3.
There were no other errors in, or changes to, the ONS LOCA analyses during this reporting period. Included in this report are LOCA PCT summary tables for Oconee Units 1, 2, and 3.
There are no regulatory commitments contained in this letter.
Please address any comments or questions regarding this matter to Paul Guill at (704) 382-4753 (paul.guill@duke-energy.corn).
Sincerely, Michael J. Annacone, Vice President - Organizational Effectiveness &
Regulatory Affairs Attachment Table 1: Mk-B-HTP Full Core Peak Cladding Temperature Summary - Oconee Units 1, 2, and 3
U.S. Nuclear Regulatory Commission July 11,2013 Page 3 xc (with attachment):
V. M. McCree, Region IIAdministrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, GA 30303-1257 J. P. Boska, Senior Project Manager (ONS)
U. S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8G9A Rockville, MD 20852-2738 E. L. Crowe NRC Senior Resident Inspector Oconee Nuclear Station
ATTACHMENT Table 1: Mk-B-HTP Full Core Peak Cladding Temperature Summary Oconee Units 1, 2, and 3 References for Table 1 A) Letter, R. M. Glover (Duke Energy) to USNRC, "30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model", December 8, 2011. [ADAMS MI1 1347A1 93]
B) Letter, B. C. Waldrep (Duke Energy) to USNRC, "Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model", July 5, 2012. [ADAMS ML121910319]
C) Letter, B. C. Waldrep (Duke Energy) to USNRC, "30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model", December 20, 2012.
D) Letter, G. J. St.Clair (AREVA) to S. B. Thomas (Duke Energy), "10 CFR 50.46 LOCA Report of Two EM Error Corrections (AREVA CR 20120165: ECCS Bypass Mathematical Error and AREVA CR 2012-757: Upper Plenum Column Weldment EM Change)", Dated February 23, 2012, AREVA Letter FAB12-120.
E) Letter, D. C. Culp (Duke Energy) to USNRC, "30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model", March 9, 2012. [ADAMS ML12073A354]
F) Letter, G. D. Miller (Duke Energy) to USNRC,
Subject:
Oconee Nuclear Station - Response to NRC RAI regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident Analysis, December 7, 2012. [ADAMS ML12348A055]
G) Letter, G. D. Miller (Duke Energy) to USNRC,
Subject:
Oconee Nuclear Station - Response to NRC RAI regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident Analysis, April 4, 2013. [ADAMS ML13102A033]
Page 1 of 2
Table 1: Mk-B-HTP Full Core Peak Cladding Temperature Summary - Oconee Units 1, 2 & 3 LBLOCA PCT(°F) Comments Evaluation model: RELAP5/MOD2-B&W Analysis of record PCT 1913 References A, B, C Prior errors (APCT)
- 1. None 0 Prior evaluation model changes (APCT)
- 1. None 0 Errors (APCT) References D, E, F, G
- 1. Error in ECCS Bypass Calculation -80 Evaluation model changes (APCT) References D, E, F, G
- 1. Upper Plenum Column Weldment Modeling +80 Absolute value of errors/changes for this report (APCT) 0 Net change in PCT for this report 0 Final PCT 1913 SBLOCA Full Power -100% FP PCT(°F) Comments Evaluation model: RELAP5/MOD2-B&W Analysis of record PCT 1598 References A, B, C (2 HPI Case) 0.15 ft 2 break Prior errors (APCT)
- 1. None 0 Prior evaluation model changes (APCT)
- 1. None 0 Errors (APCT)
- 1. None 0 Evaluation model changes (APCT) References D, E, F, G
- 1. Upper Plenum Column Weldment Modeling 0 Absolute value of errors/changes for this report (APCT) 0 Net change in PCT for this report 0 Final PCT 1598 SBLOCA Reduced Power- 50% FP [1] PCT(°F) Comments Analysis of record PCT N/A Will be reported under a separate LAR (References A, B, C)
Prior errors (APCT) N/A Prior evaluation model changes (APCT) N/A Errors (APCT) N/A Evaluation model changes (APCT) References D, E, F, G
- 1. Upper Plenum Column Weldment Modeling 0 Absolute value of errors/changes for this report (APCT) N/A Net change in PCT for this report N/A Final PCT N/A Operation Not Justified [2]
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 Cl and C2.
- 2. Pending review and approval of separate LAR. Refer to Reference A for additional details.
Page 2 of 2
