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Category:Annual Report
MONTHYEARND-21-0337, 10 CFR 50.46 Annual Report2021-04-0101 April 2021 10 CFR 50.46 Annual Report NL-19-1091, CFR 72.48(d)(2) Biennial Report2019-09-25025 September 2019 CFR 72.48(d)(2) Biennial Report NL-12-1957, 10 CFR 50.46 ECCS Evaluation Model, Annual Report for 2011 and Significant Change/Error Report2012-10-18018 October 2012 10 CFR 50.46 ECCS Evaluation Model, Annual Report for 2011 and Significant Change/Error Report ML1112200852011-04-29029 April 2011 Joseph M. Farley, Units 1 and 2, and Vogtle, Units 1 and 2, Annual Radioactive Effluent Release Reports for 2010, Cover Letter Through Page 2-25 NL-11-0811, Edwin I. Hatch, Units 1 and 2, Joseph M. Farley, Units 1 and 2, and Vogtle, Units 1 and 2, Annual Radioactive Effluent Release Reports for 2010, Cover Letter Through Page 2-252011-04-29029 April 2011 Edwin I. Hatch, Units 1 and 2, Joseph M. Farley, Units 1 and 2, and Vogtle, Units 1 and 2, Annual Radioactive Effluent Release Reports for 2010, Cover Letter Through Page 2-25 NL-11-0811, Annual Radioactive Effluent Release Reports for 2010, Page 2-26 Through End2011-04-29029 April 2011 Annual Radioactive Effluent Release Reports for 2010, Page 2-26 Through End NL-09-1150, Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2009-07-29029 July 2009 Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-08-1093, Transmittal of Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2008-07-30030 July 2008 Transmittal of Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-05-1222, Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2005-07-27027 July 2005 Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) ML0513800592005-05-11011 May 2005 Annual Radiological Environmental Operating Report for 2004, Enclosure 3 NL-05-0762, Edwin 1. Hatch, Joseph M. Farley and Vogtle - Annual Radioactive Effluent Release Reports for 20042005-04-25025 April 2005 Edwin 1. Hatch, Joseph M. Farley and Vogtle - Annual Radioactive Effluent Release Reports for 2004 NL-04-0978, Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2004-07-30030 July 2004 Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-04-1042, Plan Joseph M. Farley Nuclear Plant, and Vogtle Electric Generating Plant, 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 20032004-06-29029 June 2004 Plan Joseph M. Farley Nuclear Plant, and Vogtle Electric Generating Plant, 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2003 NL-03-0999, 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 20022003-06-0202 June 2003 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2002 NL-03-1047, Report of Facility Changes, Tests & Experiments2003-05-14014 May 2003 Report of Facility Changes, Tests & Experiments NL-03-0918, Southern Nuclear Operating Co, Inc. Annual Radioactive Effluent Release Reports for 2002, Enclosure 3, Appendix a, Chapters 3 - 102003-04-28028 April 2003 Southern Nuclear Operating Co, Inc. Annual Radioactive Effluent Release Reports for 2002, Enclosure 3, Appendix a, Chapters 3 - 10 NL-03-0938, Southern Nuclear Operating Co. Inc, Annual Radiological Environmental Operating Reports for 2002, Enclosure 3, Table of Contents Through Section 6.02003-04-28028 April 2003 Southern Nuclear Operating Co. Inc, Annual Radiological Environmental Operating Reports for 2002, Enclosure 3, Table of Contents Through Section 6.0 ML0208604442002-03-22022 March 2002 10 CFR 50.46 ECCS Evaluation Models 2001 Annual Report 2021-04-01
[Table view] Category:Letter type:NL
MONTHYEARNL-24-0031, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R232024-01-29029 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R23 NL-24-0020, Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report2024-01-22022 January 2024 Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error NL-23-0878, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0827, Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.142023-11-17017 November 2023 Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.14 NL-23-0750, Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr2023-10-0404 October 2023 Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr NL-23-0745, Refueling Outage 1R24 Steam Generator Tube Inspection Report2023-09-22022 September 2023 Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0695, Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2)2023-08-31031 August 2023 Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2) NL-23-0666, License Amendment Request: Remove Combined License Appendix C (LAR 23-008)2023-08-28028 August 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-008) NL-23-0670, Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-08-11011 August 2023 Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0672, Licensee Guarantees of Payment of Deferred Premiums2023-08-10010 August 2023 Licensee Guarantees of Payment of Deferred Premiums NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0611, Core Operating Limits Report, Cycle 11 Version 12023-07-19019 July 2023 Core Operating Limits Report, Cycle 11 Version 1 NL-23-0584, Preservice Inspection Program Owner'S Activity Report2023-07-10010 July 2023 Preservice Inspection Program Owner'S Activity Report NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications NL-23-0541, Inservice Inspection Program Owners Activity Report for Outage 1R242023-06-28028 June 2023 Inservice Inspection Program Owners Activity Report for Outage 1R24 NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0339, Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1)2023-06-13013 June 2023 Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1) NL-23-0455, Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report2023-06-12012 June 2023 Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report NL-23-0467, Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1)2023-06-0909 June 2023 Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1) NL-23-0346, License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007)2023-05-25025 May 2023 License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007) NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0385, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1)2023-05-17017 May 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1) NL-23-0398, Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)2023-05-16016 May 2023 Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006) NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0360, Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-05-0505 May 2023 Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel NL-23-0326, Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-1082023-05-0101 May 2023 Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-108 NL-23-0217, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-022023-05-0101 May 2023 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-02 NL-23-0330, Core Operating Limits Report, Cycle 25, Version 12023-04-26026 April 2023 Core Operating Limits Report, Cycle 25, Version 1 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 NL-23-0135, License Amendment Request: Timing of Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005)2023-04-17017 April 2023 License Amendment Request: Timing of Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005) NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0152, License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-04-11011 April 2023 License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0136, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)2023-04-0505 April 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006) NL-23-0132, License Amendment Request: Remove Combined License Appendix C (LAR 23-001)2023-04-0404 April 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-001) NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0193, Request for License Amendment: Relocation of TS 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003)2023-03-24024 March 2023 Request for License Amendment: Relocation of TS 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003) NL-23-0196, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902023-03-24024 March 2023 Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023 Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-22-0977, License Amendment Request to Modify Technical Specification 5.5.11.c Acceptance Criteria for Charcoal Filter Testing2023-02-0909 February 2023 License Amendment Request to Modify Technical Specification 5.5.11.c Acceptance Criteria for Charcoal Filter Testing NL-23-0010, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902023-02-0606 February 2023 Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 NL-23-0076, Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004)2023-01-31031 January 2023 Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004) NL-23-0013, Response to Request for Additional Information Related to 10CFR 50.75 Decommissioning Funding Assurance Requirements2023-01-30030 January 2023 Response to Request for Additional Information Related to 10CFR 50.75 Decommissioning Funding Assurance Requirements NL-23-0068, Responses to NRC Request for Additional Information Related to the Refueling Outage 2R22 Steam Generator Tube Inspection Report2023-01-27027 January 2023 Responses to NRC Request for Additional Information Related to the Refueling Outage 2R22 Steam Generator Tube Inspection Report NL-23-0012, Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-01-20020 January 2023 Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel 2024-01-29
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Text
Mark J. Ajluni, P.E. Southern Nuclear Nuclear Licensing Director Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7673 Fax 205 992.7885 SOUTHERN ' \ '
COMPANY October 18, 2012 Docket Nos.: 50-424 NL-12-1957 50-425 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2011 and Significant Change/Error Report Ladies and Gentlemen:
In accordance with the requirements of 10 CFR 50.46(a)(3)(ii), Southern Nuclear Operating Company (SNC) is submitting the enclosed Vogtle Electric Generating Plant Units 1 & 2 (VEGP) emergency core cooling system (ECCS) evaluation model significant change/error report.
On September 20, 2012, SNC received notification from its fuel vendor, Westinghouse Electric Company LLC (Westinghouse), of a change/error report which included the estimated effect on the VEGP limiting ECCS analysis fuel peak cladding temperature (PCT) for the large-break loss-of-coolant accident (LBLOCA) evaluation model. The estimated effect of this change/error report has been added to the estimated effects of the changes/errors previously reported in the annual report. The resultant accumulation of the absolute magnitudes of the applicable change/error estimated effects is greater than 50°F. This accumulation constitutes a significant change/error requiring a 30 day report, which is provided in Enclosure 1. Details of this change/error report are provided in Enclosure 2.
The resulting VEGP PCT continues to meet the criterion of 10 CFR 50.46(b)(1)
(i.e., ~ 2200 OF) with sufficient margin such that no reanalysis is required .
The requirements of 10 CFR 50.46(a)(3)(ii) also include an annual report by licensees of changes to, or errors in, acceptable ECCS models that affect the temperature calculation and the estimated effect of changes or errors on the limiting ECCS analysis. Accordingly, Enclosure 1 also includes a summary of changes/errors for 2011 for both the VEGP LBLOCA and the VEGP small-break loss-of-coolant accident (SBLOCA).
U. S. Nuclear Commission NL-12-1957 Page 2 This letter contains no NRC commitments. If you any questions, please contact Ken McElroy (205) 992-7369.
Respectfully submitted, M. J. Ajluni Nuclear Licensing MJAlRMJ/lac
Enclosure:
- 1. Generating Plant 10 CFR 50.46 ECCS Evaluation Annual Report for 2011 & Change/Error
- 2. Evaluation of Fuel Thermal Conductivity and Peaking cc: Southern Nuclear Operating Company Mr. S. Kuczynski, Chairman, President &
Mr. D. Vice President & Nuclear Officer Mr. T. E. Tynan, President - Vogtle Mr. B. L. Ivey, Vice President - Regulatory Mr. B. J. Adams, Vice President - Fleet RType: CVC7000 Senior Project
...."".,,1"\ .. Resident Inspector
Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2011 and Signi'ficant Change/Error Report Enclosure 1 Electric Generating Annual Report for to NL-12-1957 Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2011 & Significant Change/Error Report Vogtle Electric Generating Plant - Unit 1 BASH Large Break LOCA Evaluation Table 1-1a - Current Changes/Errors Estimated Description Effect (Ll PCT)
Westinghouse Notification Letter LTR-LlS-12-514 documents the effects of fuel pellet thermal conductivity degradation (TCD) and assembly power/peaking factor burndown in the Vogtle Units 1 and 2 Appendix K large-break loss-of-coolant accident (LBLOCA) analysis. The evaluation incorporated the approved loss of 22 coolant best estimate analysis of reflood transients (LOCBART)
Transient Extension Method (TEM). The effects of updates to the codes and methods (denoted as a "rebaseline" of the analysis of record (AOR)), combined with the effects of the combined pellet TCD and assembly power/peaking factor burndown, was 22°F.
Table 1-1 b - Summary of Changes/Errors (2011)
Estimated Description Effect (Ll PCT)
None affecting PCT N/A Table 1-1c - Cumulative Impact of Changes/Errors LljPCTI Description (OF)
- Changes/Errors Previously Reported (Reference 1) 40
- Summary of Changes/Errors (2011) (Reference 2) 0
- Current Changes/Errors (Reference 3) 22 Cumulative Total 62 E1-1
Enclosure to NL-12-1957 Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Significant VogUe Electric Generating Plant - Unit 1 Appendix K Small lOCA Table 1-1d - Summary of Changes/Errors (2011)
Estimated Description Effect (f1 PCT)
None affecting PCT N/A Table 1-1e - Cumulative Description
- Changes/Errors Previously Reported 1) o
- Changes/Errors 2011 o Cumulative 'Total I o E1
50.46 ECCS Evaluation Model Significant Change/Error Report Generating Plant Unit 2 Break lOCA Evaluation
- Current Changes/Errors Estimated Description Effect (Ll PCT)
Westinghouse Notification 4 documents of fuel pellet (TCD)
~C!c:,onr.h power/peaking Vogtle Units 1 and 2 Appendix K loss-of-coolant accident (LBLOCA) analysis. The evaluation incorporated the approved loss of 22 coolant best estimate analysis of reflood transients (LOCBART)
Transient Extension Method (TEM). The of updates to and methods (denoted as a "rebaseline" the analysis of record (AOR>>, combined with the effects of combined pellet assembly power/peaking factor was Table 1-2b - Summary of Changes/Errors (2011)
Estimated Description Effect (Ll PCT)
None ing PCT N/A Table 1-2c - Cumulative Impact of Changes/Errors
- Changes/Errors Previously Reported 40
- Summary of Changes/Errors (2011) (Reference o
- Changes/Errors (Reference 3) 22 Cumulative 62 E1-3 to NL-12-1 Vogtle Generating 10 50.46 ECCS Evaluation Model Significant Change/Error Report Vogtle Generating Plant - Unit 2 Appendix K Small Break LOCA Evaluation Table 1 - Summary of Changes/Errors (2011)
II lien"""",
Description Effect (t,. PCT)
None affecting PCT N/A Table - Cumulative Impact Changes/Errors t,.IPCTI Description (OF)
- Changes/Errors Previously Reported [R~ft:r t:r rl,;t: 1) 0
- Summary of Changes/Errors (2011) (Reference 0 Cumulative Total 0
-4 to 2-1957 Vogtle Electric Generating Plant 10 CFR ECCS Evaluation Model Significant Change/Error Report
References:
- 1. from Mark J. Ajluni to USNRC (NL-11-2402), "Edwin I. Hatch'll""""';""
Plant, M. Farley Nuclear Vogtle Electric Generating Plant 10 CFR 50.46 Evaluation Model Annual Reports for 2010," dated December 21,
- 2. Westinghouse Letter LTR-LlS-12-90, "A. W. Vogtle Units 1 and 10 CFR 50.46 Annual Notification and Reporting for 2011 ," dated February 22, 2 Westinghouse Notification Letter LTR-LlS-1 "Vogtle Units 1 and 2 10 CFR Notification and Reporting for Fuel Pellet Thermal Conductivity Degradation and Peaking Factor Burndown," dated September 2 E1-5
Vogtle Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2011 and Significant Report Enclosure 2 BASH-EM Evaluation of Pellet Thermal Conductivity Degradation and Peaking Factor Burndown to I\IL-12-1957 BASH-EM Evaluation of Fuel Pellet Thermal Conductivity Degradation and Peaking Factor Burndown
Background
Evaluations have been completed to estimate the effect of fuel pellet thermal conductivity degradation (TCD) on peak cladding temperature (PCT) for analyses using the 1981 Westinghouse large-break loss-of-coolant accident (LBLOCA) evaluation model with BASH [BART and System Hydraulics] (BASH-EM) with the loss of coolant best estimate analysis of reflood transients (LOCBART) Transient Extension Method. These evaluations utilized fuel rod performance input from a version of the Performance Analysis and Design (PAD) code that accounts for pellet TCD and that considered the beneficial effects of assembly power and peaking factor burndown resulting from the depletion of fissionable isotopes.
Affected Evaluation Model(s) 1981 Westinghouse Large-Break LOCA Evaluation Model with BASH Estimated Effect The estimated effect was determined on a plant-specific basis. The effects of updates to the codes and methods (denoted as a "rebaseline" of the analysis of record (AOR)) was 22°F, while the effects of the combined pellet TCD and assembly power/peaking factor burndown was OaF. The peaking factor burndown used in the evaluation is provided in Table 1; it is conservative for the current cycle and will be validated as part of the reload design process. SI\IC and Westinghouse utilize processes which ensure that the corresponding LOCA analysis input parameters conservatively bound the as-operated plant values.
Table 1: Peaking Factors Assumed in the Evaluation of TCD Rod Burnup FlIH (1 ,~) Fa (1)
(GWD/MTU) 0 1.65 2.50 30 1.65 2.50 60 1.40 2.00 62 1.40 2.00
- 1. Includes uncertainties
- 2. Hot assembly average power (P HA ) follows the same burndown since it is a function of FllH FlIH == l\Iuclear Enthalpy Rise Hot Channel Factor Fa ::: Heat Flux Hot Channel Factor E2-1