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| {{#Wiki_filter:Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 December 4, 2008 FIPL L-2008-254 10 CFR 50.46 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re: St. Lucie Unit 1 Docket No. 50-33 5 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Change Report During the fall 2008 SL1-22 refueling outage, Florida Power and Light (FPL) observed reduced low pressure safety injection (LPSI) flow during operation of the shutdown cooling system.This flow reduction would also be present during the injection phase of a loss of coolant accident (LOCA). The subsequent calculation that assessed the effects of this condition, along with other-previous changes and errors in the accident analysis, resulted in a new peak cladding temperature (PCT) value within the regulatory | | {{#Wiki_filter:Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 December 4, 2008 FIPL L-2008-254 10 CFR 50.46 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re: St. Lucie Unit 1 Docket No. 50-33 5 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Change Report During the fall 2008 SL1-22 refueling outage, Florida Power and Light (FPL) observed reduced low pressure safety injection (LPSI) flow during operation of the shutdown cooling system. |
| 'limit of 2200 'F provided in 10 CFR 50.46. However, the accumulated effect on PCT was greater than 50 'F.According to 10 CFR 50.46, when a cumulative PCT change in errors or changes to the analysis of 50 'F occurs, a 30 day report shall be sent to the NRC with a proposed schedule for providing reanalysis or taking action as may be needed to show compliance with 50.46 requirements. | | This flow reduction would also be present during the injection phase of a loss of coolant accident (LOCA). The subsequent calculation that assessed the effects of this condition, along with other |
| This information is provided in the attachment to this letter.Please contact Ken Frehafer at (772) 467-7748 should you have any questions regarding this submittal. | | -previous changes and errors in the accident analysis, resulted in a new peak cladding temperature (PCT) value within the regulatory 'limit of 2200 'F provided in 10 CFR 50.46. However, the accumulated effect on PCT was greater than 50 'F. |
| Sincerely, Eric S. Katzman Licensing Manager St. Lucie Plant ESK/KWF Attachment 74 -)6)an FPL Group company St. Lucie Unit 1 L-2008-254 Docket No. 50-335 Attachment 10 CFR 50.46 Change Report Page 1 of 2 St. Lucie Unit 1 10 CFR 50.46 30-Day Change Report Emergency core cooling system (ECCS) analyses for St. Lucie Unit 1 are performed by AREVA NP Inc.The following 30-Day report pertaining to the application of AREVA NP Inc. large break loss of coolant accident (LBLOCA) evaluation model SEM/PWR-98 to St. Lucie Unit 1, is provided pursuant to 10 CFR 50.46(a)(3). | | According to 10 CFR 50.46, when a cumulative PCT change in errors or changes to the analysis of 50 'F occurs, a 30 day report shall be sent to the NRC with a proposed schedule for providing reanalysis or taking action as may be needed to show compliance with 50.46 requirements. This information is provided in the attachment to this letter. |
| A summary of calculated peak cladding temperature (PCT) changes is provided in Table 1 below.1.0 Change to LPSI flow and Impact on LBLOCA 1.1 One change to the LBLOCA ECCS evaluation model analysis was done which involved a reduction of 300 gpm in the low pressure safety injection (LPSI) pump flow used in the analysis of record. The reanalysis was performed as a result of LPSI flow rate anomalies observed during operation of the shutdown cooling system during refueling outage operations. | | Please contact Ken Frehafer at (772) 467-7748 should you have any questions regarding this submittal. |
| This change resulted in an estimated effect on the peak cladding temperature (PCT) of +12 'F based on the SEM/PWR-98 evaluation model. With this change, the cumulative effect of the changes/errors on the LBLOCA evaluation model PCT for St. Lucie Unit 1 was determined to be 56 'F.Previous LBLOCA PCT changes are documented in Reference 2.1. Table 1 summarizes the estimated impact of the changes/errors on the St. Lucie Unit 1 LBLOCA PCT. The limiting LBLOCA PCT with the estimated effect of all the changes/errors is 2059 'F.1.2 The sum of the St. Lucie Unit 1 LBLOCA PCT from the most recent analyses using the accepted evaluation methodology and the estimates of PCT impact for changes and errors identified since the last analysis (2059 'F) continues to comply with the 10 CFR 50.46 acceptance criterion of 2200 'F. Therefore, no reanalysis of LBLOCA event is necessary. | | Sincerely, Eric S. Katzman Licensing Manager St. Lucie Plant ESK/KWF Attachment 74 -)6) an FPL Group company |
| 1.3 The LBLOCA event will be reanalyzed as part of the ongoing Extended Power Uprate (EPU)project, and is tentatively scheduled to be complete by end of year 2009.2.0 References 2.1 FPL Letter L-2008-046, Gordon L. Johnston to USNRC Document Control Desk, "St. Lucie Units 1 and 2, Docket Nos. 50-335 and 50-389, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors: | | |
| 10 CFR 50.46 Annual Report," March 18, 2008. | | St. Lucie Unit 1 L-2008-254 Docket No. 50-335 Attachment 10 CFR 50.46 Change Report Page 1 of 2 St. Lucie Unit 1 10 CFR 50.46 30-Day Change Report Emergency core cooling system (ECCS) analyses for St. Lucie Unit 1 are performed by AREVA NP Inc. |
| St. Lucie Unit 1 Docket No. 50-335 10 CFR 50.46 Change Report L-2008-254 Attachment Page 2 of 2 Table 1: St. Lucie Unit 1 LBLOCA PCT Margin Summary Sheet- 30 Day Report Evaluation Model: Evaluation Model PCT: EMF-2087(P)(A) | | The following 30-Day report pertaining to the application of AREVA NP Inc. large break loss of coolant accident (LBLOCA) evaluation model SEM/PWR-98 to St. Lucie Unit 1, is provided pursuant to 10 CFR 50.46(a)(3). A summary of calculated peak cladding temperature (PCT) changes is provided in Table 1 below. |
| Revision 0 (SEM/PWR-98) 2005 OF Net PCT Effect Absolute PCT Effect A. Prior 10 CFR 50.46 Changes or Error APCT + 42 0 F + 44 0 F Corrections | | 1.0 Change to LPSI flow and Impact on LBLOCA 1.1 One change to the LBLOCA ECCS evaluation model analysis was done which involved a reduction of 300 gpm in the low pressure safety injection (LPSI) pump flow used in the analysis of record. The reanalysis was performed as a result of LPSI flow rate anomalies observed during operation of the shutdown cooling system during refueling outage operations. This change resulted in an estimated effect on the peak cladding temperature (PCT) of +12 'F based on the SEM/PWR-98 evaluation model. With this change, the cumulative effect of the changes/errors on the LBLOCA evaluation model PCT for St. Lucie Unit 1 was determined to be 56 'F. |
| -Previous Years Prior 10 CFR 50.46 Changes or Error B.',C + 0°OF + 0°OF Corrections | | Previous LBLOCA PCT changes are documented in Reference 2.1. Table 1 summarizes the estimated impact of the changes/errors on the St. Lucie Unit 1 LBLOCA PCT. The limiting LBLOCA PCT with the estimated effect of all the changes/errors is 2059 'F. |
| -Year 2008 CF Current 10 CFR 50.46 Changes: -This Report LPSI Flow Reduction APCT + 12 OF + 12 OF D. Absolute Sum of 10 CFR 50.46 Changes APCT + 56 OF Final PCT with 10 CR 50.46 Changes: 2059 OF}} | | 1.2 The sum of the St. Lucie Unit 1 LBLOCA PCT from the most recent analyses using the accepted evaluation methodology and the estimates of PCT impact for changes and errors identified since the last analysis (2059 'F) continues to comply with the 10 CFR 50.46 acceptance criterion of 2200 'F. Therefore, no reanalysis of LBLOCA event is necessary. |
| | 1.3 The LBLOCA event will be reanalyzed as part of the ongoing Extended Power Uprate (EPU) project, and is tentatively scheduled to be complete by end of year 2009. |
| | 2.0 References 2.1 FPL Letter L-2008-046, Gordon L. Johnston to USNRC Document Control Desk, "St. Lucie Units 1 and 2, Docket Nos. 50-335 and 50-389, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors: 10 CFR 50.46 Annual Report," March 18, 2008. |
| | |
| | St. Lucie Unit 1 L-2008-254 Docket No. 50-335 Attachment 10 CFR 50.46 Change Report Page 2 of 2 Table 1: St. Lucie Unit 1 LBLOCA PCT Margin Summary Sheet- 30 Day Report Evaluation Model: EMF-2087(P)(A) Revision 0 (SEM/PWR-98) |
| | Evaluation Model PCT: 2005 OF Net PCT Absolute Effect PCT Effect A. Prior 10 CFR 50.46 Changes or Error APCT + 42 0 F + 44 0 F Corrections - Previous Years Prior 10 B.',C CFR 50.46 Changes or Error + 0°OF + 0°OF Corrections - Year 2008 CF Current 10 CFR 50.46 Changes: - |
| | This Report LPSI Flow Reduction APCT + 12 OF + 12 OF D. Absolute Sum of 10 CFR 50.46 Changes APCT + 56 OF Final PCT with 10 CR 50.46 Changes: 2059 OF}} |
|
|---|
Category:Fuel Cycle Reload Report
MONTHYEARL-2023-039, Cycle 27 Core Operating Limits Report2023-03-0707 March 2023
Cycle 27 Core Operating Limits Report
L-2022-125, Cycle 31 Core Operating Limits Report2022-09-0606 September 2022
Cycle 31 Core Operating Limits Report
L-2021-187, Cycle 26 Core Operating Limits Report2021-09-10010 September 2021
Cycle 26 Core Operating Limits Report
L-2021-077, Cycle 30 Core Operating Limits Report2021-04-26026 April 2021
Cycle 30 Core Operating Limits Report
L-2020-034, Cycle 25 Core Operating Limits Report2020-02-28028 February 2020
Cycle 25 Core Operating Limits Report
L-2019-196, Cycle 29 Core Operating Limits Report2019-10-30030 October 2019
Cycle 29 Core Operating Limits Report
L-2018-167, Cycle 24 Core Operating Limits Report2018-09-12012 September 2018
Cycle 24 Core Operating Limits Report
L-2018-083, Cycle 28 Core Operating Limits Report2018-04-0202 April 2018
Cycle 28 Core Operating Limits Report
L-2017-072, Submittal of Cycle 23 Startup Report2017-04-27027 April 2017
Submittal of Cycle 23 Startup Report
L-2016-190, Submittal of Core Operating Limits Report for Cycle 272016-10-14014 October 2016
Submittal of Core Operating Limits Report for Cycle 27
L-2016-048, Submittal of Cycle 22 Core Operating Limits Report2016-02-29029 February 2016
Submittal of Cycle 22 Core Operating Limits Report
L-2015-265, Cycle 22 Core Operating Limits Report2015-10-0808 October 2015
Cycle 22 Core Operating Limits Report
L-2015-114, Cycle 26 Core Operating Limits Report2015-04-14014 April 2015
Cycle 26 Core Operating Limits Report
L-2014-091, Cycle 21 Core Operating Limits Report2014-03-28028 March 2014
Cycle 21 Core Operating Limits Report
L-2013-307, Cycle 25 Core Operating Limits Report2013-10-17017 October 2013
Cycle 25 Core Operating Limits Report
L-2012-382, Extended Power Uprate Cycle 24 Startup Report2012-10-19019 October 2012
Extended Power Uprate Cycle 24 Startup Report
L-2012-298, Cycle 24 Core Operating Limits Report2012-07-25025 July 2012
Cycle 24 Core Operating Limits Report
L-2012-083, Cycle 24 Core Operating Limits Report2012-02-27027 February 2012
Cycle 24 Core Operating Limits Report
L-2011-066, Cycle 19 Core Operating Limits Report2011-03-0303 March 2011
Cycle 19 Core Operating Limits Report
L-2011-021, License Amendment Request for Extended Power Uprate, Attachment 8; Core Operating Limits Report (COLR) Markups2011-02-25025 February 2011
License Amendment Request for Extended Power Uprate, Attachment 8; Core Operating Limits Report (COLR) Markups
L-2010-095, Cycle 23 Core Operating Limits Report2010-05-0505 May 2010
Cycle 23 Core Operating Limits Report
L-2009-116, Cycle 18 Core Operating Limits Report2009-05-11011 May 2009
Cycle 18 Core Operating Limits Report
L-2009-061, Submittal of Annual Report Acceptance Criteria for Emergency Core Cooling System Analyses for Light Water Nuclear Power Reactors2009-03-11011 March 2009
Submittal of Annual Report Acceptance Criteria for Emergency Core Cooling System Analyses for Light Water Nuclear Power Reactors
L-2008-254, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors, 10 CFR 50.46 Change Report2008-12-0404 December 2008
Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors, 10 CFR 50.46 Change Report
L-2008-244, Cycle 22 Core Operating Limits Report2008-11-0505 November 2008
Cycle 22 Core Operating Limits Report
L-2008-052, Cycle 17 Reactor Startup Physics Testing Report2008-03-26026 March 2008
Cycle 17 Reactor Startup Physics Testing Report
L-2007-183, Cycle 17 Core Operating Limits Report, Rev. 02007-11-19019 November 2007
Cycle 17 Core Operating Limits Report, Rev. 0
L-2007-121, Cycle 21 Startup Physics Testing Report2007-08-0909 August 2007
Cycle 21 Startup Physics Testing Report
L-2007-066, Transmittal of Cycle 21 Core Operating Limits Report2007-04-27027 April 2007
Transmittal of Cycle 21 Core Operating Limits Report
L-2006-128, Cycle 16 Core Operating Limits Report2006-05-25025 May 2006
Cycle 16 Core Operating Limits Report
L-2005-232, Cycle 20 Core Operating Limits Report2005-11-0909 November 2005
Cycle 20 Core Operating Limits Report
L-2004-138, Cycle 19 Core Operating Limits Report - Revision 12004-06-29029 June 2004
Cycle 19 Core Operating Limits Report - Revision 1
L-2004-076, Cycle 19 Core Operating Limits Report, Revision 02004-03-29029 March 2004
Cycle 19 Core Operating Limits Report, Revision 0
L-2003-110, Cycle 14 Core Operating Limits Report2003-05-0101 May 2003
Cycle 14 Core Operating Limits Report
L-2002-209, Cycle 18 Core Operating Limits Report - Revision 02002-10-18018 October 2002
Cycle 18 Core Operating Limits Report - Revision 0
2023-03-07
[Table view]
Category:Letter type:L
MONTHYEARL-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024
Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)
L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024
Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years
L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024
Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump
L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023
Quality Assurance Topical Report (FPL-1) Revision 30 Update
L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023
Unusual or Important Environmental Event - Turtle Mortality
L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023
License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5
L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023
Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654,
L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023
Response to 50.69 2nd Round of Rals
L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023
Subsequent License Renewal Application - Second Annual Update
L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023
Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023
Corrections to the 2022 Annual Radiological Environmental Operating Report
L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023
Correction to the 2022 Annual Radioactive Effluent Release Report
L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023
Correction to the 2020 Annual Radiological Environmental Operating Report
L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023
Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023
Report of 10 CFR 50.59 Plant Changes
L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023
Corrections to the 2021 Annual Radioactive Effluent Release Report
L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023
Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023
Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update
L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023
and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2
L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023
Preparation and Scheduling of Operator Licensing Examinations
L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023
Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump
L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023
Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches
L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023
Subsequent License Renewal Application Revision 1 - Supplement 6
L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023
In-Service Inspection Program Owner'S Activity Report (OAR-1)
L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023
Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)
L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023
Subsequent License Renewal Application Revision 1, Supplement 5
L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023
Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update
L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023
NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal
L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023
Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response
L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023
2022 Annual Environmental Operating Report
L-2023-041, Annual Radiological Environmental Operating Report for Calendar Year 20222023-04-0404 April 2023
Annual Radiological Environmental Operating Report for Calendar Year 2022
L-2023-051, Report of 10 CFR 50.59 Plant Changes2023-04-0404 April 2023
Report of 10 CFR 50.59 Plant Changes
L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023
Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update
L-2023-042, Periodic Update of Population Data within 10 and 50 Miles of the Plant2023-03-27027 March 2023
Periodic Update of Population Data within 10 and 50 Miles of the Plant
L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 42023-03-27027 March 2023
Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4
L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023
and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications
L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023
Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1
L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023
and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)
L-2023-039, Cycle 27 Core Operating Limits Report2023-03-0707 March 2023
Cycle 27 Core Operating Limits Report
L-2023-032, 2022 Annual Radioactive Effluent Release Report2023-02-28028 February 2023
2022 Annual Radioactive Effluent Release Report
L-2023-038, 2022 Annual Operating Report2023-02-28028 February 2023
2022 Annual Operating Report
L-2023-016, Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan2023-02-15015 February 2023
Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan
L-2023-019, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20222023-02-15015 February 2023
Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2022
L-2023-009, Owner'S Activity Report2023-01-31031 January 2023
Owner'S Activity Report
L-2022-188, Unusual or Important Environmental Event - Turtle Mortality2022-12-19019 December 2022
Unusual or Important Environmental Event - Turtle Mortality
L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022
Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2
L-2022-175, Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-0202 December 2022
Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022
CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums
L-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022
Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response
L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022
Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2
2024-01-08
[Table view] |
Text
Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 December 4, 2008 FIPL L-2008-254 10 CFR 50.46 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re: St. Lucie Unit 1 Docket No. 50-33 5 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Change Report During the fall 2008 SL1-22 refueling outage, Florida Power and Light (FPL) observed reduced low pressure safety injection (LPSI) flow during operation of the shutdown cooling system.
This flow reduction would also be present during the injection phase of a loss of coolant accident (LOCA). The subsequent calculation that assessed the effects of this condition, along with other
-previous changes and errors in the accident analysis, resulted in a new peak cladding temperature (PCT) value within the regulatory 'limit of 2200 'F provided in 10 CFR 50.46. However, the accumulated effect on PCT was greater than 50 'F.
According to 10 CFR 50.46, when a cumulative PCT change in errors or changes to the analysis of 50 'F occurs, a 30 day report shall be sent to the NRC with a proposed schedule for providing reanalysis or taking action as may be needed to show compliance with 50.46 requirements. This information is provided in the attachment to this letter.
Please contact Ken Frehafer at (772) 467-7748 should you have any questions regarding this submittal.
Sincerely, Eric S. Katzman Licensing Manager St. Lucie Plant ESK/KWF Attachment 74 -)6) an FPL Group company
St. Lucie Unit 1 L-2008-254 Docket No. 50-335 Attachment 10 CFR 50.46 Change Report Page 1 of 2 St. Lucie Unit 1 10 CFR 50.46 30-Day Change Report Emergency core cooling system (ECCS) analyses for St. Lucie Unit 1 are performed by AREVA NP Inc.
The following 30-Day report pertaining to the application of AREVA NP Inc. large break loss of coolant accident (LBLOCA) evaluation model SEM/PWR-98 to St. Lucie Unit 1, is provided pursuant to 10 CFR 50.46(a)(3). A summary of calculated peak cladding temperature (PCT) changes is provided in Table 1 below.
1.0 Change to LPSI flow and Impact on LBLOCA 1.1 One change to the LBLOCA ECCS evaluation model analysis was done which involved a reduction of 300 gpm in the low pressure safety injection (LPSI) pump flow used in the analysis of record. The reanalysis was performed as a result of LPSI flow rate anomalies observed during operation of the shutdown cooling system during refueling outage operations. This change resulted in an estimated effect on the peak cladding temperature (PCT) of +12 'F based on the SEM/PWR-98 evaluation model. With this change, the cumulative effect of the changes/errors on the LBLOCA evaluation model PCT for St. Lucie Unit 1 was determined to be 56 'F.
Previous LBLOCA PCT changes are documented in Reference 2.1. Table 1 summarizes the estimated impact of the changes/errors on the St. Lucie Unit 1 LBLOCA PCT. The limiting LBLOCA PCT with the estimated effect of all the changes/errors is 2059 'F.
1.2 The sum of the St. Lucie Unit 1 LBLOCA PCT from the most recent analyses using the accepted evaluation methodology and the estimates of PCT impact for changes and errors identified since the last analysis (2059 'F) continues to comply with the 10 CFR 50.46 acceptance criterion of 2200 'F. Therefore, no reanalysis of LBLOCA event is necessary.
1.3 The LBLOCA event will be reanalyzed as part of the ongoing Extended Power Uprate (EPU) project, and is tentatively scheduled to be complete by end of year 2009.
2.0 References 2.1 FPL Letter L-2008-046, Gordon L. Johnston to USNRC Document Control Desk, "St. Lucie Units 1 and 2, Docket Nos. 50-335 and 50-389, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors: 10 CFR 50.46 Annual Report," March 18, 2008.
St. Lucie Unit 1 L-2008-254 Docket No. 50-335 Attachment 10 CFR 50.46 Change Report Page 2 of 2 Table 1: St. Lucie Unit 1 LBLOCA PCT Margin Summary Sheet- 30 Day Report Evaluation Model: EMF-2087(P)(A) Revision 0 (SEM/PWR-98)
Evaluation Model PCT: 2005 OF Net PCT Absolute Effect PCT Effect A. Prior 10 CFR 50.46 Changes or Error APCT + 42 0 F + 44 0 F Corrections - Previous Years Prior 10 B.',C CFR 50.46 Changes or Error + 0°OF + 0°OF Corrections - Year 2008 CF Current 10 CFR 50.46 Changes: -
This Report LPSI Flow Reduction APCT + 12 OF + 12 OF D. Absolute Sum of 10 CFR 50.46 Changes APCT + 56 OF Final PCT with 10 CR 50.46 Changes: 2059 OF
