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Category:Annual Operating Report
MONTHYEARRA-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-23-0046, Annual Radioactive Effluent Release Report - 20222023-04-24024 April 2023 Annual Radioactive Effluent Release Report - 2022 RA-22-0028, Annual Report of Changes Pursuant to 10 CFR 50.462022-04-27027 April 2022 Annual Report of Changes Pursuant to 10 CFR 50.46 RA-21-0051, Shearon Harris Nuclear Power Plant, McGuire Nuclear Station, Oconee Nuclear Station, and H. B. Robinson Steam Electric Plant - Annual Report of Changes Pursuant to 10 CFR 50.462021-04-0505 April 2021 Shearon Harris Nuclear Power Plant, McGuire Nuclear Station, Oconee Nuclear Station, and H. B. Robinson Steam Electric Plant - Annual Report of Changes Pursuant to 10 CFR 50.46 RA-20-0126, Annual Report of Changes Pursuant to 10 CFR 50.462020-05-27027 May 2020 Annual Report of Changes Pursuant to 10 CFR 50.46 MNS-18-044, Independent Spent Fuel Storage Installation (Isfsi), Submittal of 10 CFR 72.48 Summary Report from September 15, 2016 to July 26, 2018, No Changes, Tests, or Experiments2018-07-26026 July 2018 Independent Spent Fuel Storage Installation (Isfsi), Submittal of 10 CFR 72.48 Summary Report from September 15, 2016 to July 26, 2018, No Changes, Tests, or Experiments RA-18-0022, Carolinas, LLC (Duke Energy) - Annual Report of Changes Pursuant to 10 CFR 50.462018-05-24024 May 2018 Carolinas, LLC (Duke Energy) - Annual Report of Changes Pursuant to 10 CFR 50.46 CNS-18-025, Submittal of 2017 Annual Radioactive Effluent Release Report2018-04-30030 April 2018 Submittal of 2017 Annual Radioactive Effluent Release Report CNS-17-053, Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement2017-10-12012 October 2017 Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement MNS-17-037, Submittal of Summary Report of Evaluations Performed Pursuant to 10 CFR 50.59 Changes, Tests, and Experiments During the Period from January 1, 2016 to March 31, 20172017-08-10010 August 2017 Submittal of Summary Report of Evaluations Performed Pursuant to 10 CFR 50.59 Changes, Tests, and Experiments During the Period from January 1, 2016 to March 31, 2017 RA-17-0027, Duke Energy Carolinas, LLC - Annual Report of Changes Pursuant to 10 CFR 50.462017-05-25025 May 2017 Duke Energy Carolinas, LLC - Annual Report of Changes Pursuant to 10 CFR 50.46 MNS-17-020, Annual Radiological Environmental Operating Report2016-12-31031 December 2016 Annual Radiological Environmental Operating Report RA-16-0025, Duke Energy Annual Report of Changes Pursuant to 10 CFR 50.462016-05-31031 May 2016 Duke Energy Annual Report of Changes Pursuant to 10 CFR 50.46 RA-15-0029, 10 CFR 50.46 - Annual Report for 20142015-07-0707 July 2015 10 CFR 50.46 - Annual Report for 2014 ML13137A5462013-05-14014 May 2013 Submittal of 2012 Annual Radiological Environmental Operating Report ML13142A3092013-05-13013 May 2013 2012 Annual Radiological Environmental Operating Report ML13135A1332013-04-25025 April 2013 Annual Radioactive Effluent Release Report ML12157A3212012-05-31031 May 2012 Transmittal of Changes, Tests, Experiments, and Summary of Safety Evaluation Report for the Year 2011 ML12137A0112012-05-14014 May 2012 Annual Radiological Environmental Operating Report 2011 - Chapter 4.0 Through End ML12145A0502012-05-10010 May 2012 Annual Radiological Environmental Operating Report 2011, Cover Through Section 4 - Page 15 ML12145A0512012-05-10010 May 2012 Annual Radiological Environmental Operating Report 2011, Section 5 - Page 1 Through End ML12170A8672012-04-30030 April 2012 Annual Radioactive Effluent Release Report for 2011 ML12137A0122011-12-31031 December 2011 Annual Radiological Environmental Operating Report 2011 - Cover Through Chapter 3.0 ML11137A2112011-05-11011 May 2011 Annual Radiological Environmental Operating Report ML11123A0462011-04-28028 April 2011 2010 Annual Radioactive Effluent Release Report ML11143A1192010-12-31031 December 2010 Annual Radiological Environmental Operating Report ML1014001322010-05-13013 May 2010 Annual Radiological Environmental Operating Report ML1012703132010-04-29029 April 2010 2009 Annual Radioactive Effluent Release Report ML0913902862009-05-13013 May 2009 Submittal of 2008 Annual Radiological Environmental Operating Report ML0914102022009-05-13013 May 2009 Annual Radiological Environmental Operating Report for 2008 Calendar Year ML0912806102009-04-28028 April 2009 2008 Annual Radioactive Effluent Release Report ML0909603092009-03-31031 March 2009 Submittal of 2008 10CFR50.59 Description of Changes, Test, and Experiments and Summary of Safety Evaluation Report ML0908503462009-03-16016 March 2009 Duke Energy Carolinas, LLC (Duke), Catawba Nuclear Station, Units 1 and 2, Commitment Change Evaluation Report for 2008 ML0908503472009-03-16016 March 2009 Duke Energy Carolinas, LLC (Duke), McGuire Nuclear Station, Units 1 and 2, Annual Commitment Change Report ML0809401282008-03-31031 March 2008 CFR 50.59 Summary Report ML0808505592008-03-12012 March 2008 Annual Commitment Change Report NEI 99-04, McGuire Units 1 & 2, Annual Commitment Change Report2008-03-12012 March 2008 McGuire Units 1 & 2, Annual Commitment Change Report ML0710101342007-04-0303 April 2007 Commitment Change Evaluation Report for 2006 ML0710101302007-04-0303 April 2007 Submittal of 10 CFR 50.59 Summary Report for 2006 ML0710001582007-04-0303 April 2007 Annual Commitment Change Report for 2006 ML0714102372006-12-31031 December 2006 Transmittal of 2006 Annual Radiological Environmental Operating Report ML0713602092006-12-31031 December 2006 Annual Radiological Environmental Operating Report for Calendar Year 2006 ML0610200582006-04-0303 April 2006 Duke Power Company LLC D/B/A Duke Energy Carolinas, LLC Catawba Nuclear Station, Unit 1 and Unit 2 - 10 CFR 50.59 Report ML0428802082004-09-30030 September 2004 Summary Report of Evaluations Performed Pursuant to 10 CFR 50.59, Changes, Tests, and Experiments. ML0415603492004-05-26026 May 2004 Report Pursuant to 10 CFR 50.46, Changes to or Errors in an ECCS Evaluation Model for the Period from January 1, 2003 to December 31, 2003 ML0414002862004-05-12012 May 2004 Annual Radiological Environmental Operating Report ML0313506432003-05-0707 May 2003 Annual Radiological Environmental Operating Report ML0313905292003-05-0505 May 2003 Annual Radiological Environmental Operating Report - 2002 ML0313905552003-05-0505 May 2003 Annual Radiological Environmental Operating Report - 2002, 4.0 Evaluation of Dose ML0209305792002-04-0101 April 2002 CFR50.59 Annual Report for 2001 2023-04-26
[Table view] Category:Letter type:RA
MONTHYEARRA-23-0242, Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2)2024-01-10010 January 2024 Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2) RA-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-23-0295, Delay of Planned End Date for Fourth 10-Year Inservice Testing (1ST) Program Interval2024-01-0404 January 2024 Delay of Planned End Date for Fourth 10-Year Inservice Testing (1ST) Program Interval RA-23-0306, Procedures CSD-EP-BNP-0101-01, EAL Technical Basis Document, Revision 006 and CSD-EP-CNS-0101-01, EAL Technical Basis Document, Revision 005, Summary Of.2023-12-12012 December 2023 Procedures CSD-EP-BNP-0101-01, EAL Technical Basis Document, Revision 006 and CSD-EP-CNS-0101-01, EAL Technical Basis Document, Revision 005, Summary Of. 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-23-0288, End of Cycle 27 (C1 R27) Steam Generator Tube Inspection Report2023-11-16016 November 2023 End of Cycle 27 (C1 R27) Steam Generator Tube Inspection Report 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-23-0279, Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power2023-11-0202 November 2023 Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power 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-23-0230, Refuel 27 (C1 R27) Inservice Inspection (ISI) Report2023-09-25025 September 2023 Refuel 27 (C1 R27) Inservice Inspection (ISI) Report 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-23-0215, Independent Spent Fuel Storage Installation (ISFSI) ISFSI Docket Number 72-45 Registration of Spent Fuel Storage Casks2023-08-28028 August 2023 Independent Spent Fuel Storage Installation (ISFSI) ISFSI Docket Number 72-45 Registration of Spent Fuel Storage Casks 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-23-0142, 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-23-0127, 10 CFR 50.55a(g)(4)(iv) Request to Use a Subsequent Edition of ASME Section XI Referenced in 10 CFR 50.SSa(a) for ISI Code of Record2023-06-28028 June 2023 10 CFR 50.55a(g)(4)(iv) Request to Use a Subsequent Edition of ASME Section XI Referenced in 10 CFR 50.SSa(a) for ISI Code of Record RA-18-0007, License Amendment Application to Revise Control Room Cooling Technical Specifications2023-06-19019 June 2023 License Amendment Application to Revise Control Room Cooling Technical Specifications 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-23-0105, Duke Energy Carolinas, LLC (Duke Energy) - Core Operating Limits Report (COLR) for Unit 1 Cycle 28 Reload Core2023-05-0404 May 2023 Duke Energy Carolinas, LLC (Duke Energy) - Core Operating Limits Report (COLR) for Unit 1 Cycle 28 Reload Core RA-23-0118, Cycle 29, Revision 1, Core Operating Limits Report (COLR)2023-05-0303 May 2023 Cycle 29, Revision 1, Core Operating Limits Report (COLR) RA-23-0117, Report of Changes to Duke Energy McGuire Emergency Plan Annex2023-05-0101 May 2023 Report of Changes to Duke Energy McGuire Emergency Plan Annex 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-23-0046, Annual Radioactive Effluent Release Report - 20222023-04-24024 April 2023 Annual Radioactive Effluent Release Report - 2022 RA-23-0042, Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change2023-04-24024 April 2023 Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change RA-23-0091, Submittal of Emergency Action Level (EAL) Technical Basis Document, Revision 42023-04-13013 April 2023 Submittal of Emergency Action Level (EAL) Technical Basis Document, Revision 4 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-23-0084, Core Operating Limits Report (COLR) for Unit 1 Cycle 27 Reload Core, Rev. 42023-03-29029 March 2023 Core Operating Limits Report (COLR) for Unit 1 Cycle 27 Reload Core, Rev. 4 RA-23-0076, Supplement to Response to Request for Additional Information (RAI) Regarding McGuire Nuclear Station Unit 1 Spring, 2022 Outage Steam Generator Tube Inspection Report2023-03-16016 March 2023 Supplement to Response to Request for Additional Information (RAI) Regarding McGuire Nuclear Station Unit 1 Spring, 2022 Outage Steam Generator Tube Inspection Report RA-23-0083, Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core, Rev. 22023-03-16016 March 2023 Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core, Rev. 2 RA-23-0024, Response to Request for Additional Information (RAI) for Relief Request for RPV Reactor Coolant System Welds2023-02-28028 February 2023 Response to Request for Additional Information (RAI) for Relief Request for RPV Reactor Coolant System Welds RA-23-0065, Report of Changes to McGuire EAL Technical Basis Document2023-02-23023 February 2023 Report of Changes to McGuire EAL Technical Basis Document RA-18-0090, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-02-17017 February 2023 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors 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-18-0190, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-02-16016 February 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RA-23-0025, End of Cycle 28 (M1R28) Steam Generator Tube Inspection Report Response to Request for Additional Information (RAI)2023-02-15015 February 2023 End of Cycle 28 (M1R28) Steam Generator Tube Inspection Report Response to Request for Additional Information (RAI) 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-22-0608, Refuel 25 (C2R25) Inservice Inspection (ISI) Report2023-01-25025 January 2023 Refuel 25 (C2R25) Inservice Inspection (ISI) Report 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-22-0331, Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core, Rev. 12022-11-22022 November 2022 Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core, Rev. 1 RA-22-0312, Report of Changes to McGuire Emergency Plan Annex2022-10-26026 October 2022 Report of Changes to McGuire Emergency Plan Annex RA-22-0303, End of Cycle 28 (M1 R28) Steam Generator Tube Inspection Report2022-10-25025 October 2022 End of Cycle 28 (M1 R28) Steam Generator Tube Inspection Report RA-22-0291, Report of Changes to Emergency Plan Implementing Procedures2022-10-17017 October 2022 Report of Changes to Emergency Plan Implementing Procedures 2024-01-08
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Text
(~ DUKE Leo A. Martin ENERGY*
Vice President (acting)
Nuclear Engineering 526 S. Church Street Charlotte, NC 28202 Mailing Address:
EC07C I P.O. Box 1006 Charlotte, NC 28201-1006 980-373-9364 704-382-4541 fax Serial: RA-15-0029 10 CFR 50.46 July 7, 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Catawba Nuclear Station, Units 1 and 2 Docket Numbers 50-413 and 50-414/Renewed License Numbers NPF-35 and NPF-52 McGuire Nuclear Station, Units 1 and 2 Docket Numbers 50-369 and 50-370/Renewed License Numbers NPF-9 and NPF-17
Subject:
Duke Energy Carolinas, LLC (Duke Energy): 10 CFR 50.46 - Annual Report for 2014 for Catawba and McGuire Nuclear Stations
Reference:
10 CFR 50.46 (a)(3)(ii) 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, 2014, to December 31, 2014, for the Catawba Nuclear Station (CNS) and the McGuire Nuclear Station (MNS).
Several changes/errors associated with the Large Break Loss of Coolant Accident (LOCA) and Small Break LOCA evaluation models were identified during the reporting period. The specific details of these changes/errors are provided in Attachment 1, Table 1. These changes/errors were evaluated by Westinghouse as having no impact on the calculated Peak Cladding Temperature (PCT). Since there was no PCT impact due to these changes/errors, they are not included in the LOCA PCT margin summary sheets, Tables 2 through 4, for MNS Units 1 and 2 and CNS Units 1 and 2.
U.S. Nuclear Regulatory Commission RA-15-0029 Page2 There are no new regulatory commitments contained in this letter.
Please address any comments or questions regarding this matter to Michael K. Leisure at (980) 373-3619 (Mike.Leisure@duke-energy.com).
Sincerely,
~*
Leo A. Martin Vice President (acting)
Nuclear Engineering
Attachment:
2014 Annual Report of Peak Cladding Temperature
U.S. Nuclear Regulatory Commission RA-15-0029 Page 3 xc (with attachment):
V. M. McCree Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, GA 30303-1257 G. Edward Miller NRC Project Manager (Catawba & McGuire)
U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8G9A 11555 Rockville Pike Rockville, MD 20852-2738 John Zeiler NRC Senior Resident Inspector McGuire Nuclear Station G. A. Hutto, Ill NRC Senior Resident Inspector Catawba Nuclear Station
U.S. Nuclear Regulatory Commission RA-15-0029 Attachment Page 1 of 8 Attachment Duke Energy Carolinas, LLC Catawba Nuclear Station, Units 1 and 2 McGuire Nuclear Station, Units 1 and 2 10 CFR 50.46 Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors 2014 Annual Report of Peak Cladding Temperature Table 1 - Errors I Evaluation Model Changes Table 2 - LOCA Peak Cladding Temperature Margin Summary- McGuire Units 1 & 2 Table 3 - LOCA Peak Cladding Temperature Margin Summary- Catawba Unit 1 Table 4- LOCA Peak Cladding Temperature Margin Summary- Catawba Unit 2
U.S. Nuclear Regulatory Commission RA-15-0029 Attachment Page 2 of 8 Table 1 Errors I Evaluation Model Changes GENERAL CODE MAINTENANCE Affected Evaluation Models:
1996 Westinghouse Best Estimate Large Break LOCA Evaluation Model 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Various changes have been made to enhance the usability of codes and to streamline future analyses. Examples of these changes include modifying input variable definitions, units and defaults; improving the input diagnostic checks; enhancing the code output; optimizing active coding; and eliminating inactive coding. These changes represent Discretionary Changes that will be implemented on a forward-fit basis in accordance with Section 4.1.1 of WCAP-13451.
The nature of these changes leads to an estimated peak cladding temperature impact of 0 °F.
REVISED TOTAL CODE UNCERTAINTY IN BE LBLOCA MONTE CARLO SIMULATIONS Affected Evaluation Model: 1996 Westinghouse Best Estimate Large Break LOCA As part of the WCOBRA/TRAC validation basis for use in Best-Estimate (BE) Large-Break Loss-of- Coolant Accident (LBLOCA) analysis, simulations of many separate effects tests (SETs) and integral effects tests (lETs) were performed. In the Westinghouse 1996 BE LBLOCA evaluation model (COD evaluation model), the simulations of the test data which included core heat transfer measurements were used in the uncertainty methodology in two ways:
- 1. To develop heat transfer multiplier distributions which are used in the HOTSPOT code for local hot rod calculations.
- 2. To determine the minimum code uncertainties for blowdown and reflood that are used in the MONTECF code for the Monte Carlo uncertainty calculations.
The effects of several changes and error corrections to the WCOBRAITRAC code were previously reported in 2013, including effects of revised heat transfer multiplier distributions. As a result of previously reported changes and error corrections made to WCOBRA/TRAC, the total code uncertainty values utilized in the MONTECF code for both blowdown and reflood were recalculated. The recalculated total code uncertainty values are lower than the previous values.
Resolution of this issue represents a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-13451.
The total code uncertainty value is essentially a minimum limit for the superposition correction in the Monte Carlo simulations performed with the MONTECF code. As a result, a reduction in the minimum superposition correction would be expected to produce a small benefit, and will thus be conservatively assigned a 0 oF estimate of effect on peak cladding temperature.
U.S. Nuclear Regulatory Commission RA-15-0029 Attachment Page 3 of 8 FUEL ROD GAP CONDUCTANCE ERROR Affected Evaluation Model: 1985 Small Break LOCA Evaluation Model with NOTRUMP An error was identified in the fuel rod gap conductance model in the NOTRUMP computer code (reactor coolant system response model). The error is associated with the use of an incorrect temperature in the calculation of the cladding emissivity term. This error corresponds to a Non-Discretionary Change as described in Section 4.1.2 of WCAP-13451.
The estimated effect was determined based on a combination of engineering judgment of the phenomena and physics of a small break LOCA and sensitivity calculations performed with the advanced plant version of NOTRUMP. It was concluded that this error has a negligible effect on small break LOCA analysis results, leading to an estimated peak cladding temperature impact of 0 °F.
RADIATION HEAT TRANSFER MODEL ERROR Affected Evaluation Model: 1985 Small Break LOCA Evaluation Model with NOTRUMP Two errors were discovered in the calculation of the radiation heat transfer coefficient within the fuel rod model of the NOTRUMP computer code (reactor coolant system response model).
First, existing logic did not preclude non-physical negative or large (negative or positive) radiation heat transfer coefficients from being calculated. These erroneous calculations occurred when the vapor temperature exceeded the cladding surface temperature or when the predicted temperature difference was less than 1 °F. Second, a temperature term incorrectly used degrees Fahrenheit instead of Rankine. These errors represent a closely related group of Non-Discretionary problems in accordance with Section 4.1.2 of WCAP-13451.
The estimated effect was determined based on a combination of engineering judgment of the phenomena and physics of a small break LOCA and sensitivity calculations performed with the advanced plant version of NOTRUMP. It was concluded that this error has a negligible effect on small break LOCA analysis results, leading to an estimated peak cladding temperature impact of 0 °F.
U.S. Nuclear Regulatory Commission RA-15-0029 Attachment Page 4 of 8 Table 2 LOCA Peak Cladding Temperature Margin Summary- McGuire Units 1 & 2 LBLOCA Cladding Temp Comments (oF)
Evaluation model: WCOBRA!TRAC, CQD 1996 McGuire Units 1 Analysis of record PCT (Reflood 2) 2028 & 2/Catawba Units 1 & 2 Composite Model Prior errors (~PCT)
- 1. Decay heat in Monte Carlo calculations 8 Reference M
- 2. MONTECF power uncertainty correction 20 Reference B
- 3. Safety Injection temperature range 59 Reference C
- 4. Input error resulting in an incomplete solution matrix 25 ReferenceD
- 5. Revised Slowdown Heatup Uncertainty Distribution 5 Reference E
- 6. Vessel Unheated Conductor Noding 0 Reference F
- 7. Thermal Conductivity Degradation with Peaking 15 References H, I Factor Burndown
- 8. Revised Heat Transfer Multiplier Distribution -85 Reference K
- 9. HOTSPOT Clad Burst Strain Error 70 Reference L Prior evaluation model changes (~PCT)
- 1. Revised Algorithm for Average Fuel Temperature 0 Reference F
- 2. PAD 3.4 to PAD 4.0 -75 References H, I
- 3. Peak FQ = 2. 7 in bottom third of core 0 References H, I
- 4. MUR Uprate to 101.7% of 3411 MWt 16 References H, I New errors (~PCT)
- 1. None New evaluation model changes (~PCT)
- 1. None Absolute value of errors/changes for this report (~PCT) 0 Net change in PCT for this report 0 Final PCT 2086 SBLOCA Evaluation model : NOTRUMP Analysis of record PCT 1323 2 inch break, Reference G Prior errors (~PCT)
- 1. Evaluation of Fuel Pellet Thermal Conductivity 0 Reference J Degradation Prior evaluation model changes (~PCT)
- 1. None 0 New errors (~PCT)
- 1. None New evaluation model changes (~PCT)
- 1. None Absolute value of errors/changes for this report (~PCT) 0 Net change in PCT for this report 0 Final PCT 1323
U.S. Nuclear Regulatory Commission RA-15-0029 Attachment Page 5 of 8 Table 3 LOCA Peak Cladding Temperature Margin Summary- Catawba Unit 1 LBLOCA Cladding Temp Comments (oF)
Evaluation model : WCOBRA/TRAC, CQD 1996 McGuire Units 1 Analysis of record PCT (Reflood 2) 2028 & 2/Catawba Units 1 & 2 Composite Model Prior errors (~PCT)
- 1. Decay heat in Monte Carlo calculations 8 Reference A
- 2. MONTECF power uncertainty correction 20 Reference N
- 3. Safety Injection temperature range 59 Reference C
- 4. Input error resulting in an incomplete solution matrix 25 ReferenceD
- 5. Revised Slowdown Heatup Uncertainty Distribution 5 Reference E
- 6. Vessel Unheated Conductor Noding 0 Reference F
- 7. Thermal Conductivity Degradation with Peaking 15 References H, I Factor Burndown
- 8. Revised Heat Transfer Multiplier Distribution -85 Reference K
- 9. HOTSPOT Clad Burst Strain Error 70 Reference L Prior evaluation model changes (~PCT)
- 1. Revised Algorithm for Average Fuel Temperature 0 Reference F
- 2. PAD 3.4 to PAD 4.0 -75 References H, I
- 3. Peak FQ = 2.7 in bottom third of core 0 References H, I New errors (~PCT)
- 1. None New evaluation model changes (~PCT)
- 1. None Absolute value of errors/changes for this report (~PCT) 0 Net change in PCT for this report 0 Final PCT 2070 SBLOCA Evaluation model : NOTRUMP Analysis of record PCT 1323 2 inch break, Reference G Prior errors (~PCT)
- 1. Evaluation of Fuel Pellet Thermal Conductivity 0 Reference J Degradation Prior evaluation model changes (~PCT)
- 1. None 0 New errors (~PCT)
- 1. None New evaluation model changes (~PCT)
- 1. None Absolute value of errors/changes for this report (~PCT) 0 Net change in PCT for this report 0 Final PCT 1323
U.S. Nuclear Regulatory Commission RA-15-0029 Attachment Page 6 of 8 Table 4 LOCA Peak Cladding Temperature Margin Summary- Catawba Unit 2 LBLOCA Cladding Temp Comments (Of)
Evaluation model : WCOBRA!TRAC, CQD 1996 McGuire Units 1 Analysis of record PCT (Reflood 2) 2028 & 2/Catawba Units 1 & 2 Composite Model Prior errors (~PCT)
- 1. Decay heat in Monte Carlo calculations 8 Reference A
- 2. MONTECF power uncertainty correction 20 Reference N
- 3. Safety Injection temperature range 59 Reference C
- 4. Input error resulting in an incomplete solution matrix 25 ReferenceD
- 5. Revised Slowdown Heatup Uncertainty Distribution 5 Reference E
- 6. Vessel Unheated Conductor Nading 0 Reference F
- 7. Thermal Conductivity Degradation with Peaking 15 References H, I Factor Burndown
- 8. Revised Heat Transfer Multiplier Distribution -85 Reference K
- 9. HOTSPOT Clad Burst Strain Error 70 Reference L Prior evaluation model changes (~PCT)
- 1. Revised Algorithm for Average Fuel Temperature 0 Reference F
- 2. PAD 3.4 to PAD 4.0 -75 References H, I
- 3. Peak FQ =2.7 in bottom third of core 0 References H, I New errors (~PCT)
- 1. None New evaluation model changes (~PCT)
- 1. None Absolute value of errors/chanQes for this report (~PCT) 0 Net change in PCT for this report 0 Final PCT 2070 SBLOCA Evaluation model : NOTRUMP Analysis of record PCT 1243 4 inch break, Reference G Prior errors (~PCT)
- 1. Evaluation of Fuel Pellet Thermal Conductivity 0 Reference J Degradation Prior evaluation model changes (~PCT)
- 1. None 0 New errors (~PCT)
- 1. None New evaluation model changes (~PCT)
- 1. None Absolute value of errors/chanQes for this report (~PCT) 0 Net change in PCT for this report 0 Final PCT 1243
U.S. Nuclear Regulatory Commission RA-15-0029 Attachment Page 7 of 8 References for Tables 2, 3, and 4:
A) Letter, G. R. Peterson (Duke Energy) to USNRC, Report Pursuant to 10 CFR 50.46, Changes to or Errors in an EGGS Evaluation Model, April 11 , 2001. (ADAMS ML011070266)
B) Letter, M.S. Tuckman (Duke Energy) to USNRC, Report Pursuant to 10 CFR 50.46, Changes to or Errors in an EGGS Evaluation Model, April 3, 2002. (ADAMS ML021070672)
C) Letter, W. R. McCollum, Jr. (Duke Energy) to USNRC, Report Pursuant to 10 CFR 50.46, Changes to or Errors in an EGGS Evaluation Model, July 29, 2003. (ADAMS ML032170639)
D) Letter, W. R. McCollum, Jr. (Duke Energy) to USNRC, Report Pursuant to 10 CFR 50.46, Changes to or Errors in an EGGS Evaluation Model, May 26, 2004. (ADAMS ML041560349)
E) Letter, J. R. Morris (Duke Energy) to USNRC, Report Pursuant to 10 CFR 50.46, Changes to or Errors in an EGGS Evaluation Model, June 21,2005. (ADAMS ML051790210)
F) Letter, T. C. Geer (Duke Energy) to USNRC, Report Pursuant to 10 CFR 50.46, Changes to or Errors in an EGGS Evaluation Model, March 13,2007. (ADAMS ML070800546)
G) Letter, T. C. Geer (Duke Energy) to USNRC, Report Pursuant to 10 CFR 50.46, Changes to or Errors in an EGGS Evaluation Model, May 22, 2007. (ADAMS ML071500297)
H) Letter, D. C. Culp (Duke Energy) to USNRC, Response to Information Request Pursuant to 10 CFR 50.54(f) Related to the Estimated Effect on Peak Cladding Temperature Resulting from Thermal Conductivity Degradation in the Westinghouse-Furnished Realistic Emergency Core Cooling System Evaluation and 30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model, March 16, 2012. (ADAMS ML12079A180)
I) Letter, J. Thompson (USNRC) to K. Henderson and S. D. Capps (Duke Energy), Catawba Nuclear Station Units 1 and 2, and McGuire Nuclear Station Units 1 and 2, Closure Evaluation for Report Pursuant to Title 10 of the Code of Federal Regulations, Part 50, Section 50.46, Paragraph (a)(3)(ii) Concerning Significant Emergency Core Cooling System Evaluation Model Error Related to Nuclear Fuel Thermal Conductivity Degradation (TAG Nos. ME8447, ME8448, ME8449, and ME8450)," November 16, 2012. (ADAMS ML12314A031)
J) Letter, M. J. Annacone, (Duke Energy) to USNRC, Report Pursuant to 10 CFR 50.46, Changes to or Errors in an EGGS Evaluation Model, July 11, 2013. (ADAMS ML13199A279)
K) Letter, R. J. Duncan, (Duke Energy) to USNRC, Report Pursuant to 10 CFR 50.46, Changes to or Errors in an EGGS Evaluation Model, August 29, 2013. (ADAMS ML13246A103).
L) Letter, B. C. Waldrep (Duke Energy) to USNRC, Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model, February 25, 2014. (ADAMS ML14063A278)
M) Letter, M.S. Tuckman (Duke Energy) to USNRC, Report Pursuant to 10 CFR 50.46, Changes to or Errors in an EGGS Evaluation Model, May 3, 2001. (ADAMS ML011310391)
U.S. Nuclear Regulatory Commission RA-15-0029 Attachment Page 8 of 8 N) Letter, M.S. Tuckman (Duke Energy) to USNRC, Report Pursuant to 10 CFR 50.46, Changes to or Errors in an EGGS Evaluation Model, April 3, 2002. (ADAMS ML021070656)