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| {{#Wiki_filter:February 13, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 Large Break Loss-of-Coolant Accident Margin Summary Sheet-30-Day Report EXT era E N ERG Y*& POINT BEACH NRC 2014-0012 10 CFR 50.46(a)(3)(ii) | | {{#Wiki_filter:EXTera ENERGY& |
| In accordance with 1 OCFR50.46(a)(3)(ii), NextEra Energy Point Beach (NextEra), LLC, is submitting this 30-day report for the Point Beach Nuclear Plant (PBNP) Units 1 and 2 for the emergency core cooling system (ECCS) analysis performed by Westinghouse Electric Company, LLC. The following 30-day report pertaining to the application of the Westinghouse large break loss of coolant accident (LBLOCA) evaluation model is provided pursuant to 10 CFR 50.46(a)(3)(ii). | | POINT BEACH February 13, 2014 NRC 2014-0012 10 CFR 50.46(a)(3)(ii) |
| The Enclosure describes the ECCS evaluation model changes and errors to the large break loss of coolant accident (LOCA). The Table provides the large break LOCA peak cladding temperatures margin summary. This submittal contains no new commitments or revisions to existing commitments. | | U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 Large Break Loss-of-Coolant Accident Margin Summary Sheet Day Report In accordance with 1OCFR50.46(a)(3)(ii), NextEra Energy Point Beach (NextEra), LLC, is submitting this 30-day report for the Point Beach Nuclear Plant (PBNP) Units 1 and 2 for the emergency core cooling system (ECCS) analysis performed by Westinghouse Electric Company, LLC. The following 30-day report pertaining to the application of the Westinghouse large break loss of coolant accident (LBLOCA) evaluation model is provided pursuant to 10 CFR 50.46(a)(3)(ii). |
| Very truly yours, NextEra Energy Point Beach, LLC ---'--Michael Millen Licensing Manager Point Beach Nuclear Plant Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC NextEra Energy Po i nt B ea ch , LLC, 6610 Nuclear Road, Two Ri v ers , WI 54241 ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Emergency core cooling system (ECCS) analyses for Point Beach Units 1 and 2 are performed by Westinghouse Electric Company, LLC. The following 30-day report pertaining to the application of the Westinghouse large break loss of coolant accident (LBLOCA) evaluation model is provided pursuant to 10 CFR 50.46(a)(3)(ii). | | The Enclosure describes the ECCS evaluation model changes and errors to the large break loss of coolant accident (LOCA). The Table provides the large break LOCA peak cladding temperatures margin summary. |
| A summary of the calculated peak cladding temperature (PCT) changes for LBLOCA is provided in the Table. LARGE BREAK LOCA ECCS EVALUATION MODEL CHANGES AND ERRORS Error in Burst Strain Application in the HOTSPOT Code In the application of the burst strain in the HOTSPOT code, burst strain is incorrectly applied to the inner radius rather than the outer radius of the cladding, which impacts the resulting cladding geometry at the burst elevation after the burst occurs. Correction of this error results in thinner cladding at the burst location and more fuel relocation at the burst node, leading to an increase in the PCT at the burst node. | | This submittal contains no new commitments or revisions to existing commitments. |
| * The estimated impact of this error is +50 oF for Unit 1 and 0 oF for Unit 2. Previous LBLOCA PCT changes are documented in Reference 3.1. Table 1 summarizes the estimated impact of the changes/errors on the Point Beach Units 1 and 2 LBLOCA PCT, along with the cumulative effect of absolute PCT changes for both Point Beach Units. The limiting LBLOCA PCT with the estimated effect of all the changes/errors is 2185 oF and 2056 oF for Units 1 and 2, respectively. | | Very truly yours, NextEra Energy Point Beach, LLC |
| With the impact of all changes/errors, Point Beach Units 1 and Unit 2 continue to comply with the 10 CFR 50.46 acceptance criterion for PCT of | | ~~ |
| °F. Proposed Schedule The schedule for LBLOCA re-analyses is as provided previously in Reference | | --- '-- |
| : 2. References 1 NextEra Energy Point Beach, LLC letter to NRC, dated August 23, 2013, "Large Break Coolant Accident Margin Summary Sheet-30-day Report" (ML13238A222).
| | Michael Millen Licensing Manager Point Beach Nuclear Plant Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241 |
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| | ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Emergency core cooling system (ECCS) analyses for Point Beach Units 1 and 2 are performed by Westinghouse Electric Company, LLC. The following 30-day report pertaining to the application of the Westinghouse large break loss of coolant accident (LBLOCA) evaluation model is provided pursuant to 10 CFR 50.46(a)(3)(ii). A summary of the calculated peak cladding temperature (PCT) changes for LBLOCA is provided in the Table. |
| | LARGE BREAK LOCA ECCS EVALUATION MODEL CHANGES AND ERRORS Error in Burst Strain Application in the HOTSPOT Code In the application of the burst strain in the HOTSPOT code, burst strain is incorrectly applied to the inner radius rather than the outer radius of the cladding, which impacts the resulting cladding geometry at the burst elevation after the burst occurs. Correction of this error results in thinner cladding at the burst location and more fuel relocation at the burst node, leading to an increase in the PCT at the burst node. |
| | * The estimated impact of this error is +50 oF for Unit 1 and 0 oF for Unit 2. |
| | Previous LBLOCA PCT changes are documented in Reference 3.1. Table 1 summarizes the estimated impact of the changes/errors on the Point Beach Units 1 and 2 LBLOCA PCT, along with the cumulative effect of absolute PCT changes for both Point Beach Units. The limiting LBLOCA PCT with the estimated effect of all the changes/errors is 2185 oF and 2056 oF for Units 1 and 2, respectively. With the impact of all changes/errors, Point Beach Units 1 and Unit 2 continue to comply with the 10 CFR 50.46 acceptance criterion for PCT of ~2200 °F. |
| | Proposed Schedule The schedule for LBLOCA re-analyses is as provided previously in Reference 2. |
| | References 1 NextEra Energy Point Beach, LLC letter to NRC, dated August 23, 2013, "Large Break Loss-of-Coolant Accident Margin Summary Sheet- 30-day Report" (ML13238A222). |
| 2 NextEra Energy Point Beach, LLC letter to NRC, dated March 1, 2013, "Thermal Conductivity Degradation Impact on Large Break Loss of Coolant Accident Analyses with ASTRUM Response to Request for Additional Information" (ML13063A289) | | 2 NextEra Energy Point Beach, LLC letter to NRC, dated March 1, 2013, "Thermal Conductivity Degradation Impact on Large Break Loss of Coolant Accident Analyses with ASTRUM Response to Request for Additional Information" (ML13063A289) |
| Page 1 of 2 TABLE LARGE BREAK LOCA MARGIN | | Page 1 of 2 |
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| | TABLE LARGE BREAK LOCA MARGIN |
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| ==SUMMARY== | | ==SUMMARY== |
| SHEET-30-DAY REPORT Plant Name: Point Beach Units 1 and 2 2115114 Utility Name: NextEra Energy Evaluation Model: Westinghouse Realistic Large Break LOCA Evaluation Model using ASTRUM. Evaluation Model PCT (Unit 11Unit 2): A Prior 10 CFR 50.46 Changes or Error ilPCT Corrections-up to Year 2013 B Prior 10 CFR 50.46 Changes or ilPCT Errors Corrections-Year 2014 c 10 CFR 50.46 Changes in Year 2014 ilPCT Since Item B HOTSPOT error in burst strain application D Absolute Sum of 10 CFR 50.46 ilPCT Changes The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for changes and errors identified since this analysis Page 2 of 2 Net PCT Effect Absolute PCT Effect Unit 11Unit 2 Unit 11Unit 2 +160 OF I +246 OF 160 OF 1338 OF ooF I ooF OoF I ooF +50 °F I 0 OF 50 OF I 0 OF 210 °F 1338 °F}} | | SHEET- 30-DAY REPORT Plant Name: Point Beach Units 1 and 2 2115114 Utility Name: NextEra Energy Evaluation Model: Westinghouse Realistic Large Break LOCA Evaluation Model using ASTRUM. |
| | Evaluation Model PCT (Unit 11Unit 2): |
| | Absolute PCT Net PCT Effect Effect Unit 11Unit 2 Unit 11Unit 2 A Prior 10 CFR 50.46 Changes or Error ilPCT +160 OF I +246 OF 160 OF 1338 OF Corrections- up to Year 2013 B Prior 10 CFR 50.46 Changes or ilPCT ooF I ooF OoF I ooF Errors Corrections- Year 2014 c 10 CFR 50.46 Changes in Year 2014 ilPCT Since Item B HOTSPOT error in burst strain application +50 °F I 0 OF 50 OF I 0 OF D Absolute Sum of 10 CFR 50.46 ilPCT 210 °F 1338 °F Changes The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for changes and errors identified since this analysis Page 2 of 2}} |
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Category:Letter type:NRC
MONTHYEARNRC 2023-0013, Response to Regulatory Information Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-07-0707 July 2023 Response to Regulatory Information Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations NRC 2023-0006, Post-Exam Submittal Cover Letter2023-03-0101 March 2023 Post-Exam Submittal Cover Letter NRC 2023-0005, Report of Changes to Emergency Plan2023-02-21021 February 2023 Report of Changes to Emergency Plan NRC 2022-0032, Sixth 10-Year Interval Inservice Testing (1ST) Program Plan2022-09-30030 September 2022 Sixth 10-Year Interval Inservice Testing (1ST) Program Plan NRC 2022-0025, License Amendment Request 295, Beacon Power Distribution Monitoring System2022-09-26026 September 2022 License Amendment Request 295, Beacon Power Distribution Monitoring System NRC 2022-0019, Report of Changes to Emergency Plan2022-07-13013 July 2022 Report of Changes to Emergency Plan NRC 2022-0022, Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2,2022-07-11011 July 2022 Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, NRC 2022-0015, Fall 2021 Unit 2 (U2R38) Steam Generator Tube Inspection Report2022-04-27027 April 2022 Fall 2021 Unit 2 (U2R38) Steam Generator Tube Inspection Report NRC 2022-0014, 2021 Annual Monitoring Report2022-04-14014 April 2022 2021 Annual Monitoring Report NRC 2021-0012, Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41)2022-04-0707 April 2022 Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41) NRC 2022-0003, License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process2022-03-25025 March 2022 License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process NRC 2022-0006, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2022-02-22022 February 2022 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections NRC 2022-0004, Report of Changes to Emergency Plan2022-02-0909 February 2022 Report of Changes to Emergency Plan NRC 2022-0005, Refueling Outage U2R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2022-02-0101 February 2022 Refueling Outage U2R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2022-0001, Report of Changes to Emergency Plan2022-01-11011 January 2022 Report of Changes to Emergency Plan NRC 2021-0046, Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40)2021-10-28028 October 2021 Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40) NRC 2021-0031, Registration of Holtec Hi STORM Casks HI-STORM-37-054, HI-STORM-37-055, and HI-STORM-37-0562021-07-15015 July 2021 Registration of Holtec Hi STORM Casks HI-STORM-37-054, HI-STORM-37-055, and HI-STORM-37-056 NRC 2021-0027, Registration of Holtec Historm Casks HISTORM-37-051, HISTORM-37-052, and HISTORM-37-0532021-06-30030 June 2021 Registration of Holtec Historm Casks HISTORM-37-051, HISTORM-37-052, and HISTORM-37-053 NRC 2021-0028, Generic Letter 2004-02 Containment Sump Debris Transport Calculation Non-Conservatism2021-06-23023 June 2021 Generic Letter 2004-02 Containment Sump Debris Transport Calculation Non-Conservatism NRC 2021-0021, 2020 Annual Monitoring Report2021-04-29029 April 2021 2020 Annual Monitoring Report NRC 2021-0019, Response to Regulatory Information Summary 2021-01 Preparation and Scheduling of Operator Licensing Examinations2021-04-22022 April 2021 Response to Regulatory Information Summary 2021-01 Preparation and Scheduling of Operator Licensing Examinations NRC-2021-0010, CFR 50.59 Evaluation and Commitment Change Summary Report2021-04-0202 April 2021 CFR 50.59 Evaluation and Commitment Change Summary Report NRC-2021-0011, Technical Specification Bases and Technical Requirement Manual Change Summary2021-04-0202 April 2021 Technical Specification Bases and Technical Requirement Manual Change Summary NRC 2021-0006, Report of Changes to Emergency Plan2021-03-18018 March 2021 Report of Changes to Emergency Plan NRC 2021-0005, Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 2004-022021-02-11011 February 2021 Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 2004-02 NRC 2021-0002, Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2021-01-21021 January 2021 Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2021-0003, Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report2021-01-21021 January 2021 Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report NRC 2021-0001, Report of Changes to Emergency Plan2021-01-13013 January 2021 Report of Changes to Emergency Plan NRC 2020-0044, Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise2020-12-0808 December 2020 Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise NRC 2020-0032, Application for Subsequent Renewed Facility Operating Licenses2020-11-16016 November 2020 Application for Subsequent Renewed Facility Operating Licenses NRC 2020-0039, Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40)2020-11-0202 November 2020 Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40) NRC 2020-0031, NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-0812020-10-0505 October 2020 NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-081 NRC 2020-0029, Supplement to License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-09-15015 September 2020 Supplement to License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0024, Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements2020-08-17017 August 2020 Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements NRC 2020-0020, License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-08-13013 August 2020 License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0023, NextEra Energy Point Beach, LLC - Revised Response to Regulatory Information Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations2020-08-12012 August 2020 NextEra Energy Point Beach, LLC - Revised Response to Regulatory Information Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations NRC 2020-0021, Response to NRC Inspection Report and Preliminary White Finding2020-08-12012 August 2020 Response to NRC Inspection Report and Preliminary White Finding NRC 2020-0018, Report of Changes to Emergency Plan2020-07-15015 July 2020 Report of Changes to Emergency Plan NRC-2020-0016, Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic2020-06-12012 June 2020 Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic NRC 2020-0012, Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2020-05-20020 May 2020 Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2020-0008, Report of Changes to Emergency Plan2020-04-0606 April 2020 Report of Changes to Emergency Plan NRC 2020-0007, Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38)2020-03-27027 March 2020 Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38) NRC 2020-0003, License Amendment Request 289: Tornado Missile Protection Licensing Basis2020-02-0606 February 2020 License Amendment Request 289: Tornado Missile Protection Licensing Basis NRC 2020-0001, Pressure Temperature Limits Report (PTLR)2020-01-0909 January 2020 Pressure Temperature Limits Report (PTLR) NRC 2019-0044, Report of Changes to Emergency Plan2019-11-0101 November 2019 Report of Changes to Emergency Plan NRC 2019-0036, Submittal of 2018 Update to Final Safety Analysis Report2019-10-18018 October 2019 Submittal of 2018 Update to Final Safety Analysis Report NRC 2019-0037, Technical Specification Bases Change Summary2019-10-18018 October 2019 Technical Specification Bases Change Summary NRC 2019-0034, Technical Requirements Manual Change Summary2019-10-18018 October 2019 Technical Requirements Manual Change Summary NRC 2019-0032, CFR 50.59 Evaluation and Commitment Change Summary Report2019-10-18018 October 2019 CFR 50.59 Evaluation and Commitment Change Summary Report NRC 2019-0042, NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information2019-10-17017 October 2019 NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information 2023-07-07
[Table view] Category:Licensee 30-Day Written Event Report
MONTHYEARL-2019-058, CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2019-03-25025 March 2019 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2018-063, CFR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications2018-03-26026 March 2018 CFR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications NRC-2017-0012, Submitting 10 CFR 26.719(c) Report on Inaccurate Reporting of Laboratory Test Result2017-02-24024 February 2017 Submitting 10 CFR 26.719(c) Report on Inaccurate Reporting of Laboratory Test Result L-2016-124, 10 CFR 50.46 30-Day Report for Turkey Point, Seabrook, and Point Beach2016-06-17017 June 2016 10 CFR 50.46 30-Day Report for Turkey Point, Seabrook, and Point Beach NRC 2016-0015, Large Break Loss-of-Coolant Accident Margin Summary Sheet - 30-Day Report2016-04-0606 April 2016 Large Break Loss-of-Coolant Accident Margin Summary Sheet - 30-Day Report NRC 2014-0086, 10 CFR 50.46 30-Day Report2014-12-11011 December 2014 10 CFR 50.46 30-Day Report NRC 2014-0029, CFR 50.46 Annual Report/30-Day Report2014-04-18018 April 2014 CFR 50.46 Annual Report/30-Day Report NRC 2014-0012, Large Break Loss-of-Coolant Accident Margin Summary Sheet - 30-Day Report2014-02-13013 February 2014 Large Break Loss-of-Coolant Accident Margin Summary Sheet - 30-Day Report NRC 2013-0081, Large Break Loss-of Coolant Accident Margin Summary Sheet- 30-Day Report2013-08-23023 August 2013 Large Break Loss-of Coolant Accident Margin Summary Sheet- 30-Day Report NRC 2012-0038, ECCS 30-Day Report for the Thermal Conductivity Degradation Impact on Large Break Loss of Coolant Accident Analyses with Astrum2012-05-30030 May 2012 ECCS 30-Day Report for the Thermal Conductivity Degradation Impact on Large Break Loss of Coolant Accident Analyses with Astrum NRC-2007-0055, Error Identified in ECCS Evaluation Model 30-Day Report Required by 10 CFR 50.462007-07-0303 July 2007 Error Identified in ECCS Evaluation Model 30-Day Report Required by 10 CFR 50.46 ML0508303282004-05-0606 May 2004 Event Notification 40728 for Point Beach NRC 2003-0042, Reporting of Fire Barriers Degraded for More than Seven Days2003-05-0909 May 2003 Reporting of Fire Barriers Degraded for More than Seven Days NRC 2002-0095, Reporting of Fire Barriers Degraded for More than Seven Days2002-10-22022 October 2002 Reporting of Fire Barriers Degraded for More than Seven Days NRC 2002-0083, Reporting of Fire Barriers Degraded for More than Seven Days2002-09-26026 September 2002 Reporting of Fire Barriers Degraded for More than Seven Days ML0307702772002-08-0707 August 2002 2-page Abnormal Occurrence Writeup for 11/29/2001 Event Potential Loss of All Auxiliary Feedwater at Point Beach Plant 2019-03-25
[Table view] |
Text
EXTera ENERGY&
POINT BEACH February 13, 2014 NRC 2014-0012 10 CFR 50.46(a)(3)(ii)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 Large Break Loss-of-Coolant Accident Margin Summary Sheet Day Report In accordance with 1OCFR50.46(a)(3)(ii), NextEra Energy Point Beach (NextEra), LLC, is submitting this 30-day report for the Point Beach Nuclear Plant (PBNP) Units 1 and 2 for the emergency core cooling system (ECCS) analysis performed by Westinghouse Electric Company, LLC. The following 30-day report pertaining to the application of the Westinghouse large break loss of coolant accident (LBLOCA) evaluation model is provided pursuant to 10 CFR 50.46(a)(3)(ii).
The Enclosure describes the ECCS evaluation model changes and errors to the large break loss of coolant accident (LOCA). The Table provides the large break LOCA peak cladding temperatures margin summary.
This submittal contains no new commitments or revisions to existing commitments.
Very truly yours, NextEra Energy Point Beach, LLC
~~
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Michael Millen Licensing Manager Point Beach Nuclear Plant Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241
ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Emergency core cooling system (ECCS) analyses for Point Beach Units 1 and 2 are performed by Westinghouse Electric Company, LLC. The following 30-day report pertaining to the application of the Westinghouse large break loss of coolant accident (LBLOCA) evaluation model is provided pursuant to 10 CFR 50.46(a)(3)(ii). A summary of the calculated peak cladding temperature (PCT) changes for LBLOCA is provided in the Table.
LARGE BREAK LOCA ECCS EVALUATION MODEL CHANGES AND ERRORS Error in Burst Strain Application in the HOTSPOT Code In the application of the burst strain in the HOTSPOT code, burst strain is incorrectly applied to the inner radius rather than the outer radius of the cladding, which impacts the resulting cladding geometry at the burst elevation after the burst occurs. Correction of this error results in thinner cladding at the burst location and more fuel relocation at the burst node, leading to an increase in the PCT at the burst node.
- The estimated impact of this error is +50 oF for Unit 1 and 0 oF for Unit 2.
Previous LBLOCA PCT changes are documented in Reference 3.1. Table 1 summarizes the estimated impact of the changes/errors on the Point Beach Units 1 and 2 LBLOCA PCT, along with the cumulative effect of absolute PCT changes for both Point Beach Units. The limiting LBLOCA PCT with the estimated effect of all the changes/errors is 2185 oF and 2056 oF for Units 1 and 2, respectively. With the impact of all changes/errors, Point Beach Units 1 and Unit 2 continue to comply with the 10 CFR 50.46 acceptance criterion for PCT of ~2200 °F.
Proposed Schedule The schedule for LBLOCA re-analyses is as provided previously in Reference 2.
References 1 NextEra Energy Point Beach, LLC letter to NRC, dated August 23, 2013, "Large Break Loss-of-Coolant Accident Margin Summary Sheet- 30-day Report" (ML13238A222).
2 NextEra Energy Point Beach, LLC letter to NRC, dated March 1, 2013, "Thermal Conductivity Degradation Impact on Large Break Loss of Coolant Accident Analyses with ASTRUM Response to Request for Additional Information" (ML13063A289)
Page 1 of 2
TABLE LARGE BREAK LOCA MARGIN
SUMMARY
SHEET- 30-DAY REPORT Plant Name: Point Beach Units 1 and 2 2115114 Utility Name: NextEra Energy Evaluation Model: Westinghouse Realistic Large Break LOCA Evaluation Model using ASTRUM.
Evaluation Model PCT (Unit 11Unit 2):
Absolute PCT Net PCT Effect Effect Unit 11Unit 2 Unit 11Unit 2 A Prior 10 CFR 50.46 Changes or Error ilPCT +160 OF I +246 OF 160 OF 1338 OF Corrections- up to Year 2013 B Prior 10 CFR 50.46 Changes or ilPCT ooF I ooF OoF I ooF Errors Corrections- Year 2014 c 10 CFR 50.46 Changes in Year 2014 ilPCT Since Item B HOTSPOT error in burst strain application +50 °F I 0 OF 50 OF I 0 OF D Absolute Sum of 10 CFR 50.46 ilPCT 210 °F 1338 °F Changes The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for changes and errors identified since this analysis Page 2 of 2