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Category:Letter type:SBK
MONTHYEARSBK-L-23053, Radiological Emergency Plan (Ssrep), Revision 802023-06-22022 June 2023 Radiological Emergency Plan (Ssrep), Revision 80 SBK-L-23031, 2022 Annual Radioactive Effluent Release Report2023-04-28028 April 2023 2022 Annual Radioactive Effluent Release Report SBK-L-23044, 2022 Annual Radiological Environmental Operating Report2023-04-28028 April 2023 2022 Annual Radiological Environmental Operating Report SBK-L-23033, 2022 Annual Environmental Operating Report2023-04-11011 April 2023 2022 Annual Environmental Operating Report SBK-L-22093, 75 Day and 150 Day Submittal Letters2022-12-0101 December 2022 75 Day and 150 Day Submittal Letters SBK-L-22113, Radiological Emergency Plan (Ssrep), Revision 792022-11-16016 November 2022 Radiological Emergency Plan (Ssrep), Revision 79 SBK-L-22114, Independent Spent Fuel Storage Installation (Isfsi), Cask Registration2022-11-0909 November 2022 Independent Spent Fuel Storage Installation (Isfsi), Cask Registration SBK-L-22112, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2022-11-0303 November 2022 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration SBK-L-22094, Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)2022-10-26026 October 2022 Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) SBK-L-22105, Supplement to 2021 Annual Radioactive Effluent Release Report2022-10-24024 October 2022 Supplement to 2021 Annual Radioactive Effluent Release Report SBK-L-22103, 5 to the Physical Security Plan, Training and Qualification Plan and Safeguards Contingency Plan2022-10-12012 October 2022 5 to the Physical Security Plan, Training and Qualification Plan and Safeguards Contingency Plan SBK-L-22102, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2022-10-0606 October 2022 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration SBK-L-22080, Submittal of 10 CFR 72.48 Report of Changes, Tests and Experiments for August 2020 to July 20222022-08-12012 August 2022 Submittal of 10 CFR 72.48 Report of Changes, Tests and Experiments for August 2020 to July 2022 SBK-L-22054, SBK-L-22054 - License Amendment Request 22-01, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-06-0909 June 2022 SBK-L-22054 - License Amendment Request 22-01, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections SBK-L-22044, 2021 Annual Radioactive Effluent Release Report2022-04-29029 April 2022 2021 Annual Radioactive Effluent Release Report SBK-L-22036, Steam Generator Tube Inspection Report2022-04-25025 April 2022 Steam Generator Tube Inspection Report SBK-L-22040, Radiological Emergency Plan (Ssrep), Revision 7822022-04-20020 April 2022 Radiological Emergency Plan (Ssrep), Revision 782 SBK-L-22024, Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2022-03-0707 March 2022 Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements SBK-L-22003, Inservice Inspection Examination Report2022-01-24024 January 2022 Inservice Inspection Examination Report SBK-L-21126, Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan2022-01-0404 January 2022 Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan SBK-L-21135, Submittal of Changes to the Seabrook Station Technical Specification Bases2021-12-29029 December 2021 Submittal of Changes to the Seabrook Station Technical Specification Bases SBK-L-21108, Core Operating Limits Report for Cycle 222021-11-0404 November 2021 Core Operating Limits Report for Cycle 22 SBK-L-21106, Transmittal of WCAP-18607-NP, Analysis of Capsule X from the NextEra Energy Seabrook Unit 1 Reactor Vessel Radiation Surveillance Program2021-09-30030 September 2021 Transmittal of WCAP-18607-NP, Analysis of Capsule X from the NextEra Energy Seabrook Unit 1 Reactor Vessel Radiation Surveillance Program SBK-L-21105, Withdrawal of Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink One-Time Allowed Outage Time (AOT) Extension2021-09-27027 September 2021 Withdrawal of Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink One-Time Allowed Outage Time (AOT) Extension SBK-L-21103, Request for Exercise of Enforcement Discretion2021-09-25025 September 2021 Request for Exercise of Enforcement Discretion SBK-L-21104, Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink Onetime Allowed Outage Time (AOT) Extension2021-09-25025 September 2021 Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink Onetime Allowed Outage Time (AOT) Extension SBK-L-21098, Supplement to License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2021-09-22022 September 2021 Supplement to License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements SBK-L-21083, NextEra Energy Seabrook, LLC - Relief Request 3IR-18 and 3IR-19 for End of Third 10-Year ISI Interval for Examinations with Limited Coverage2021-08-18018 August 2021 NextEra Energy Seabrook, LLC - Relief Request 3IR-18 and 3IR-19 for End of Third 10-Year ISI Interval for Examinations with Limited Coverage SBK-L-21067, License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2021-07-21021 July 2021 License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements SBK-L-21049, Revision to Updated Final Response to NRC Generic Letter 2004-022021-06-24024 June 2021 Revision to Updated Final Response to NRC Generic Letter 2004-02 SBK-L-21056, Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review References:2021-05-20020 May 2021 Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review References: SBK-L-21045, Submittal of 2020 Annual Radioactive Effluent Release Report2021-04-30030 April 2021 Submittal of 2020 Annual Radioactive Effluent Release Report SBK-L-21044, 2020 Annual Radiological Environmental Operating Report2021-04-30030 April 2021 2020 Annual Radiological Environmental Operating Report SBK-L-21042, Response to RIS 2021-01 Preparation and Scheduling of Operator Licensing Examinations2021-04-22022 April 2021 Response to RIS 2021-01 Preparation and Scheduling of Operator Licensing Examinations SBK-L-21033, Response to Request for Additional Information (RAI) Regarding License Amendment Request (LAR) 20-02, Resolve Non-Conservative Heat Flux Hot Channel Factor (Fo(Z)) Requirements2021-03-24024 March 2021 Response to Request for Additional Information (RAI) Regarding License Amendment Request (LAR) 20-02, Resolve Non-Conservative Heat Flux Hot Channel Factor (Fo(Z)) Requirements SBK-L-21023, Radiological Emergency Plan (Ssrep), Revision 772021-03-0404 March 2021 Radiological Emergency Plan (Ssrep), Revision 77 SBK-L-20154, Submittal of Changes to the Seabrook Station Technical Specification Bases2020-12-22022 December 2020 Submittal of Changes to the Seabrook Station Technical Specification Bases SBK-L-20149, Response to Request for Additional Information in Respect to One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-12-0808 December 2020 Response to Request for Additional Information in Respect to One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic SBK-L-20146, One-Time Exemption Request for the Biennial Emergency Preparedness Exercise Requirements of 10 CFR 50, Appendix E. IV.F.2.b and IV.F.2.c2020-12-0303 December 2020 One-Time Exemption Request for the Biennial Emergency Preparedness Exercise Requirements of 10 CFR 50, Appendix E. IV.F.2.b and IV.F.2.c SBK-L-20144, Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-23023 November 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic SBK-L-20143, Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 004-022020-11-19019 November 2020 Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 004-02 SBK-L-20132, Fourth Interval Inservice Testing (IST) Program2020-10-21021 October 2020 Fourth Interval Inservice Testing (IST) Program SBK-L-20127, Generator Tube Inspection Report2020-10-20020 October 2020 Generator Tube Inspection Report SBK-L-20117, Response to Request for Additional Information Regarding Technical Specification 3/4.8.1 for a One-Time Extension of Allowed Outage Time License Amendment Request2020-09-23023 September 2020 Response to Request for Additional Information Regarding Technical Specification 3/4.8.1 for a One-Time Extension of Allowed Outage Time License Amendment Request SBK-L-20103, Inservice Inspection Examination Report2020-07-27027 July 2020 Inservice Inspection Examination Report SBK-L-20092, Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-411 and TSTF-4182020-07-13013 July 2020 Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-411 and TSTF-418 SBK-L-20068, License Amendment Request 20-01, One-Time Change to the Seabrook Technical Specifications A.C. Sources - Operating2020-07-13013 July 2020 License Amendment Request 20-01, One-Time Change to the Seabrook Technical Specifications A.C. Sources - Operating SBK-L-20085, Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic2020-06-16016 June 2020 Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic SBK-L-20077, Core Operating Limits Report for Cycle 212020-06-0101 June 2020 Core Operating Limits Report for Cycle 21 SBK-L-20057, Response to Request for Additional Information Regarding Degraded Voltage Time Delay Setpoint License Amendment Request2020-05-20020 May 2020 Response to Request for Additional Information Regarding Degraded Voltage Time Delay Setpoint License Amendment Request 2023-06-22
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-2023-064, License Amendment Request 23-01, Revision 1, Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves2023-05-11011 May 2023 License Amendment Request 23-01, Revision 1, Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves L-2023-012, License Amendment Request 23-01, Remove Period of Applicability (Poa) from Pressure Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves2023-03-15015 March 2023 License Amendment Request 23-01, Remove Period of Applicability (Poa) from Pressure Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves L-2022-176, License Amendment Request to Revise Cooling Tower Service Water Loop or Cell Requirements2022-12-0909 December 2022 License Amendment Request to Revise Cooling Tower Service Water Loop or Cell Requirements 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 ML22200A1082022-07-19019 July 2022 Acceptance Review for TSTF-577 Amendment SBK-L-21135, Submittal of Changes to the Seabrook Station Technical Specification Bases2021-12-29029 December 2021 Submittal of Changes to the Seabrook Station Technical Specification Bases SBK-L-21098, Supplement to License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2021-09-22022 September 2021 Supplement to License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements SBK-L-21067, License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2021-07-21021 July 2021 License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements SBK-L-20068, License Amendment Request 20-01, One-Time Change to the Seabrook Technical Specifications A.C. Sources - Operating2020-07-13013 July 2020 License Amendment Request 20-01, One-Time Change to the Seabrook Technical Specifications A.C. Sources - Operating ML20120A0472020-04-29029 April 2020 Correction to Amendment No. 162 Issued November 18, 2019, Revisions to Technical Specifications Associated with Movable Control Rods SBK-L-20001, License Amendment Request 19-03, Application to Revise Degraded Voltage Time Delay Setpoint2020-01-24024 January 2020 License Amendment Request 19-03, Application to Revise Degraded Voltage Time Delay Setpoint SBK-L-18089, License Amendment Request 17-06, Change to the Technical Specification Requirements for Reactor Trip System Instrumentation and Engineered Safety Features Actuation System Instrumentation to Implement WCAP-14333 and WCAP-153762019-11-0101 November 2019 License Amendment Request 17-06, Change to the Technical Specification Requirements for Reactor Trip System Instrumentation and Engineered Safety Features Actuation System Instrumentation to Implement WCAP-14333 and WCAP-15376 SBK-L-19104, License Amendment Request 19-02, One-Time Change to the Seabrook Technical Specifications Onsite Power Distribution Requirements2019-10-0303 October 2019 License Amendment Request 19-02, One-Time Change to the Seabrook Technical Specifications Onsite Power Distribution Requirements SBK-L-19049, License Amendment Request 19-01, Application to Revise the Technical Specifications Associated with Emergency Core Cooling System Accumulators2019-06-0404 June 2019 License Amendment Request 19-01, Application to Revise the Technical Specifications Associated with Emergency Core Cooling System Accumulators SBK-L-18151, Supplement 61 - Additional Changes to the NextEra Energy Seabrook License Renewal Application2018-08-29029 August 2018 Supplement 61 - Additional Changes to the NextEra Energy Seabrook License Renewal Application L-2018-049, Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications2018-05-29029 May 2018 Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications SBK-L-18075, Eighth Annual Update to License Renewal Application2018-05-0101 May 2018 Eighth Annual Update to License Renewal Application SBK-L-18013, Nextera Energy Seabrook - License Amendment Request 18-01, Application to Revise Frequencies in the Control Room Habitability Program2018-03-16016 March 2018 Nextera Energy Seabrook - License Amendment Request 18-01, Application to Revise Frequencies in the Control Room Habitability Program SBK-L-18006, Additional Change to Seventh Annual Update to the NextEra Energy Seabrook License Renewal Application2018-01-23023 January 2018 Additional Change to Seventh Annual Update to the NextEra Energy Seabrook License Renewal Application SBK-L-17185, License Amendment Request 17-04: Remove Limitation to Perform Certain Surveillance Requirements During Shutdown and Changes to Administrative Technical Specifications2017-12-0101 December 2017 License Amendment Request 17-04: Remove Limitation to Perform Certain Surveillance Requirements During Shutdown and Changes to Administrative Technical Specifications SBK-L-17163, Supplement 57 - Revision to License Renewal Application 10 CFR 50 Appendix J Program2017-10-0606 October 2017 Supplement 57 - Revision to License Renewal Application 10 CFR 50 Appendix J Program SBK-L-17081, License Amendment Request 17-02, Change to the Technical Specifications Requirement for DC Batteries2017-07-28028 July 2017 License Amendment Request 17-02, Change to the Technical Specifications Requirement for DC Batteries SBK-L-17108, Supplement 56 - Revision to License Renewal ASME Section XI, Subsection Iwl, Program Operating Experience2017-07-20020 July 2017 Supplement 56 - Revision to License Renewal ASME Section XI, Subsection Iwl, Program Operating Experience L-2017-041, Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month,' Using the Consolidated Line Item Improvement Process2017-03-30030 March 2017 Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month,' Using the Consolidated Line Item Improvement Process ML17046A4432017-03-15015 March 2017 Issuance of Amendment Extension of Containment Leakage Rate Test Frequency SBK-L-16181, License Renewal Application Relating to the Alkali-Silica Reaction Monitoring Program2016-12-23023 December 2016 License Renewal Application Relating to the Alkali-Silica Reaction Monitoring Program SBK-L-16146, Sixth Annual Update to the Renewal Application2016-10-0707 October 2016 Sixth Annual Update to the Renewal Application SBK-L-16013, License Renewal Application Relating to the Alkali-Silica Reaction Monitoring Program2016-08-0909 August 2016 License Renewal Application Relating to the Alkali-Silica Reaction Monitoring Program ML16216A2412016-07-31031 July 2016 MPR-4288, Revision 0, Seabrook Station: Impact of Alkali-Silica Reaction on Structural Design Evaluations, July 2016 ML16216A2422016-07-31031 July 2016 MPR-4273, Revision 0, Seabrook Station - Implications of Large-Scale Test Program Results on Reinforced Concrete Affected by Alkali-Silica Reaction, July 2016 SBK-L-16071, Sg&H Report 160268-R-01 Development of ASR Load Factors for Seismic Category I Structures (Including Containment) at Seabrook Station. Seabrook, Nh Revision 02016-07-27027 July 2016 Sg&H Report 160268-R-01 Development of ASR Load Factors for Seismic Category I Structures (Including Containment) at Seabrook Station. Seabrook, Nh Revision 0 ML15310A1022015-11-19019 November 2015 License Renewal Application Online Reference Portal SBK-L-15187, Supplement 43 - Responses to Request for Additional Information Related to the Review of the License Renewal Application - Set 242015-10-0909 October 2015 Supplement 43 - Responses to Request for Additional Information Related to the Review of the License Renewal Application - Set 24 SBK-L-15093, License Amendment Request (LAR) 15-01, Application to Add a Note to Technical Specification TS 4.4.1.3.42015-07-13013 July 2015 License Amendment Request (LAR) 15-01, Application to Add a Note to Technical Specification TS 4.4.1.3.4 SBK-L-14155, License Amendment Request 14-06 - Change to the Technical Specifications to Remove the Cold Leg Injection Permissive (P-15)2014-09-24024 September 2014 License Amendment Request 14-06 - Change to the Technical Specifications to Remove the Cold Leg Injection Permissive (P-15) SBK-L-14126, Station,Proposed Change to Increase Voltage Limit for Diesel Generator Load Rejection Surveillance Requirement2014-07-24024 July 2014 Station,Proposed Change to Increase Voltage Limit for Diesel Generator Load Rejection Surveillance Requirement SBK-L-14080, Changes to Technical Specification 3.3.3.1. Radiation Monitoring for Plant Operations2014-07-24024 July 2014 Changes to Technical Specification 3.3.3.1. Radiation Monitoring for Plant Operations ML14167A4302014-06-12012 June 2014 Supplement to License Amendment Request 13-05, Fixed Incore Detector System Analysis Methodology SBK-L-14086, Nextera Energy Seabrook - Letter Regarding Response to Requests for Additional Information for the Review of the License Renewal Application Set 20 Relating to the Alkali-Silica Reaction (ASR) Monitoring Program2014-05-15015 May 2014 Nextera Energy Seabrook - Letter Regarding Response to Requests for Additional Information for the Review of the License Renewal Application Set 20 Relating to the Alkali-Silica Reaction (ASR) Monitoring Program SBK-L-13224, Request for Review and Approval of License Amendment Request (LAR) 11-04, Changes to Technical Specifications for New and Spent Fuel Storage, in Two Parts2013-12-20020 December 2013 Request for Review and Approval of License Amendment Request (LAR) 11-04, Changes to Technical Specifications for New and Spent Fuel Storage, in Two Parts SBK-L-13121, License Amendment Request 13-05, Fixed Incore Detector System Analysis Methodology2013-09-10010 September 2013 License Amendment Request 13-05, Fixed Incore Detector System Analysis Methodology SBK-L-13030, LAR 13-02 - Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process2013-03-27027 March 2013 LAR 13-02 - Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process SBK-L-13028, License Amendment Request 13-01 Application for Administrative Change and Corrections to the Technical Specifications2013-03-0101 March 2013 License Amendment Request 13-01 Application for Administrative Change and Corrections to the Technical Specifications SBK-L-12235, License Amendment Request 12-06, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process2012-12-20020 December 2012 License Amendment Request 12-06, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process SBK-L-12186, Second Annual Update to the NextEra Energy Seabrook License Renewal Application2012-09-18018 September 2012 Second Annual Update to the NextEra Energy Seabrook License Renewal Application SBK-L-12105, License Amendment Request 12-03, Cyber Security Plan Implementation Schedule Milestone Change2012-06-20020 June 2012 License Amendment Request 12-03, Cyber Security Plan Implementation Schedule Milestone Change SBK-L-12101, NextEra Energy Seabrook License Renewal Application, Structures Monitoring Program Supplement-Alkali-Silica Reaction (ASR) Monitoring2012-05-16016 May 2012 NextEra Energy Seabrook License Renewal Application, Structures Monitoring Program Supplement-Alkali-Silica Reaction (ASR) Monitoring SBK-L-12062, License Amendment Request 12-01 Proposed Changes to Emergency Action Levels Regarding Safety System Indications2012-04-30030 April 2012 License Amendment Request 12-01 Proposed Changes to Emergency Action Levels Regarding Safety System Indications SBK-L-12072, License Amendment Request 12-02, Request for Permanent Application of Steam Generator Tube Alternate Repair Criteria, H2012-04-10010 April 2012 License Amendment Request 12-02, Request for Permanent Application of Steam Generator Tube Alternate Repair Criteria, H SBK-L-11245, License Amendment Request 11-04, Changes to the Technical Specifications for New and Spent Fuel Storage2012-01-30030 January 2012 License Amendment Request 11-04, Changes to the Technical Specifications for New and Spent Fuel Storage 2023-05-11
[Table view] Category:Technical Specifications
MONTHYEARSBK-L-22024, Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2022-03-0707 March 2022 Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements ML20293A1572020-12-28028 December 2020 Issuance of Amendment No. 167 Reactor Trip System Instrumentation Technical Specification Changes to Implement WCAP-14333 and WCAP-15376 ML19326C4802019-12-0505 December 2019 Issuance of Amendment No. 163 One-Time Change to the Onsite Power Distribution Requirements SBK-L-19104, License Amendment Request 19-02, One-Time Change to the Seabrook Technical Specifications Onsite Power Distribution Requirements2019-10-0303 October 2019 License Amendment Request 19-02, One-Time Change to the Seabrook Technical Specifications Onsite Power Distribution Requirements ML18228A7372018-08-31031 August 2018 Correction Letter for Amendment No. 157 Changes to the Technical Specifications Requirements for DC Batteries (CAC No. MG0046; EPID L-2017-LLA-0289) L-2018-049, Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications2018-05-29029 May 2018 Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications ML15096A2552015-11-0202 November 2015 Issuance of Amendment Regarding License Amendment Request 14-04, Revised Reactor Coolant System Pressure-Temperature Limits Applicable for 44 Effective Full Power Years ML15231A1442015-10-0606 October 2015 Issuance of Amendment No. 150 Regarding Note for Reactor Coolant System Surveillance Requirements SBK-L-15183, LER, Seabrook Station - Technical Specification Special Report Radiation Monitor Inoperable Greater than 7 Days2015-09-25025 September 2015 LER, Seabrook Station - Technical Specification Special Report Radiation Monitor Inoperable Greater than 7 Days ML15096A1312015-07-17017 July 2015 Issuance of Amendment Regarding Changes to Technical Specification 3.3.3.1, Radiation Monitoring for Plant Operations ML15118A6322015-05-18018 May 2015 Issuance of Amendment Regarding License Amendment Request Regarding New Fuel Valut ML15082A2332015-04-24024 April 2015 Issuance of Amendment Regarding Increase Voltage Limit for Diesel Generator Load Rejection Surveillance Requirement ML15058A7062015-04-22022 April 2015 Issuance of Amendment No. 146 Regarding the Cyber Security Plan Implementation Schedule ML14345A2882015-02-0606 February 2015 Issuance of Amendment Regarding Technical Specifications Task Force Traveler-523, Generic Letter 2008-01, Managing Gas Accumulation Using the Consolidated Line Item Improvement Process ML14363A2752015-02-0404 February 2015 Non-Proprietary SE for Issuance of Amendment Regarding License Amendment Request Regarding Fixed Incore Detector System Analysis ML14184A7952014-09-0303 September 2014 Issuance of Amendment Regarding License Amendment Request Regarding Fuel Storage Changes ML13212A0692014-07-24024 July 2014 Issuance of Amendment Regarding the Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program ML14029A4452014-03-0606 March 2014 Issuance of Amendment Regarding License Amendment Request 12-04, Application Regarding Cold Leg Injection Permissive SBK-L-13121, License Amendment Request 13-05, Fixed Incore Detector System Analysis Methodology2013-09-10010 September 2013 License Amendment Request 13-05, Fixed Incore Detector System Analysis Methodology ML1130000632013-04-23023 April 2013 Issuance of Amendment Addition of Action Statement to Limiting Condition for Operation 3.6.5.1, Containment Enclosure Emergency Air Cleanup System SBK-L-13061, Response to December 2012 Request for Additional Information Regarding License Amendment Request 11-04, Changes to Technical Specifications for New and Spent Fuel Storage2013-03-27027 March 2013 Response to December 2012 Request for Additional Information Regarding License Amendment Request 11-04, Changes to Technical Specifications for New and Spent Fuel Storage SBK-L-13030, LAR 13-02 - Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process2013-03-27027 March 2013 LAR 13-02 - Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process SBK-L-12266, Supplement to License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System2013-01-31031 January 2013 Supplement to License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System SBK-L-12235, License Amendment Request 12-06, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process2012-12-20020 December 2012 License Amendment Request 12-06, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process SBK-L-11130, License Amendment Request 11-03, Regarding Containment Spray Nozzles Surveillance Requirement2011-07-14014 July 2011 License Amendment Request 11-03, Regarding Containment Spray Nozzles Surveillance Requirement SBK-L-09196, License Amendment Request to Revise Technical Specification (TS) Sections 6.7.6.k, Steam Generator (SG) Program and TS 6.8.1.7, Steam Generator Tube Inspection Report for One-Time Alternate Repair Criteria2009-09-18018 September 2009 License Amendment Request to Revise Technical Specification (TS) Sections 6.7.6.k, Steam Generator (SG) Program and TS 6.8.1.7, Steam Generator Tube Inspection Report for One-Time Alternate Repair Criteria ML0819102622008-07-30030 July 2008 Technical Specifications, Issuance of Amendment Nuclear Instrumentation Surveillance Requirements ML0812000612008-04-29029 April 2008 Tec Specs to Amendment 118, License No. NPF-086, for Seabrook, Unit 1 ML0804606942008-03-27027 March 2008 Tech Spec Pages for Amendment 117 Setpoint Change for Reactor Trip System Interlock P-9 SBK-L-07142, Correction to License Amendment Request (LAR) 07-02, Application to Revise the Technical Specifications Regarding Control Room Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-10-15015 October 2007 Correction to License Amendment Request (LAR) 07-02, Application to Revise the Technical Specifications Regarding Control Room Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0723901902007-08-23023 August 2007 Tech Spec Pages for Amendment 116 Technical Specification Task Force (TSTF)-449, Steam Generator Tube Integrity. SBK-L-07112, License Amendment Request 07-02, Application to Revise the Technical Specifications Regarding Control Room Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process.2007-07-17017 July 2007 License Amendment Request 07-02, Application to Revise the Technical Specifications Regarding Control Room Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process. ML0708802862007-03-28028 March 2007 Technical Specifications, Issuance of Amendment Regarding TSTF -449 Steam Generator Tube Integrity TAC No. MD0696 ML0704704742007-02-0909 February 2007 Technical Specifications, Issuance of Amendment Mode Change Limitations ML0629902612006-10-17017 October 2006 Tech Spec Pages for Amendment 113 Removal of License Condition 2.G ML0627501812006-09-29029 September 2006 Technical Specifications, Limited Inspection of the Steam Generator Tube Portion within the Tubesheet SBK-L-06157, Response to Request for Additional Information Regarding License Amendment Request 05-08 Limited Inspection of the Steam Generator Tube Portion within the Tubesheet.2006-08-0808 August 2006 Response to Request for Additional Information Regarding License Amendment Request 05-08 Limited Inspection of the Steam Generator Tube Portion within the Tubesheet. SBK-L-06059, License Amendment Request 06-03 Application for Amendment to Technical Specifications for Miscellaneous Changes.2006-08-0707 August 2006 License Amendment Request 06-03 Application for Amendment to Technical Specifications for Miscellaneous Changes. ML0616402492006-06-12012 June 2006 Technical Specification - Correction of Amendment No. 108, Six-Month Extension for the Containment Integrated Leakage Rate Test Interval ML0616402512006-06-0909 June 2006 Tech Spec Page for Emergency Amendment 111 Allowed Outage Time Extension from 7 Days to 14 Days for Enclosure Air Handling Fan SBK-L-06127, Emergency License Amendment Request 06-07, Containment Enclosure Emergency Air Cleanup System Allowed Outage Time One Time Change2006-06-0707 June 2006 Emergency License Amendment Request 06-07, Containment Enclosure Emergency Air Cleanup System Allowed Outage Time One Time Change ML0614402592006-05-22022 May 2006 Tech Spec Pages for Amendment 110 Regarding Measurement Uncertainty Recapture Power Uprate ML0612802822006-05-0505 May 2006 Technical Specification Pages Elimination of Monthly Operating Reports and Occupational Radiation Exposure Reports - Technical Specifications Index, 6.0 Administrative Controls SBK-L-06065, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process.2006-04-28028 April 2006 Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process. ML0610203542006-04-13013 April 2006 Tech Spec Pages for Correction of Amendment No. 107, Regarding Removal of Requirement to Perform End-of-Life Moderator Temperature Coefficient Measurement (Tac No. MC6566) ML0608601162006-03-24024 March 2006 Technical Specification Page, Revises to Permit a one-time, 6-month, Addition to the currently-approved 5-year Extension to the 10-year Test Interval for the Containment Integrated Leak Rate Test L-2006-042, 30-day Response to NRC Generic Letter 2006-01, Steam Generator Tube Integrity and Associated Technical Specifications, January 20, 20062006-02-17017 February 2006 30-day Response to NRC Generic Letter 2006-01, Steam Generator Tube Integrity and Associated Technical Specifications, January 20, 2006 ML0600904762006-01-0606 January 2006 Tech Spec Page for Amendment 106 Extension of Containment Air Lock Interlock Surveillance Requirement Interval SBK-L-05260, License Amendment Request 05-11, Changes to Technical Specification 3.8.3.1, Onsite Power Distribution, for Vital Inverter Allowed Outage Time.2005-12-0606 December 2005 License Amendment Request 05-11, Changes to Technical Specification 3.8.3.1, Onsite Power Distribution, for Vital Inverter Allowed Outage Time. SBK-L-05197, License Amendment Request 05-06 Application for Amendment to Technical Specification 6.15 for a Six Month Extension to the Containment Integrated Leak Rate Test Interval.2005-09-29029 September 2005 License Amendment Request 05-06 Application for Amendment to Technical Specification 6.15 for a Six Month Extension to the Containment Integrated Leak Rate Test Interval. 2022-03-07
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FPL Energy Seabrook Station FPL Energy P.O. Box 300 Seabrook, NH 03874 Seabrook Station (603) 773-7000 MAR 2 8 2005 SBK-L-05055 Docket No. 50-443 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Seabrook Station License Amendment Request 05-03 "Exemption from the End of Life Moderator Temperature Coefficient Measurement" FPL Energy Seabrook, LLC (FPL Energy Seabrook) has enclosed herein License Amendment Request (LAR) 05-03. License Amendment Request 05-03 is submitted pursuant to the requirements of 10 CFR 50.90 and 10 CFR 50.4.
This LAR, based on WCAP-13749-P-A, Safety Evaluation Supporting the ConditionalExemption of the Most Negative EOL Moderator Temperature Coefficent Measurement, modifies the end of life moderator temperature coefficient (MTC) surveillance requirement by allowing an exemption to the surveillance if certain conditions are met. This conditional exemption from the surveillance requirement will be determined on a cycle-specific basis by considering the predicted margin to the MTC limit and other core parameters such as beginning of life MTC measurements and critical boron concentration. This conditional exemption from the MTC measurement is sought to improve plant availability and minimize disruptions to normal plant operations.
As discussed in the enclosed LAR Section IV, the proposed change does not involve a significant hazard consideration pursuant to 10 CFR 50.92. A copy of this letter and the enclosed LAR has been forwvarded to the New Hampshire State Liaison Officer pursuant to 10 CFR 50.91(b). FPL Energy Seabrook has determined that LAR 05-03 meets the criteria of 10 CFR 51.22(c)(9) for a categorical exclusion from the requirements for an Environmental Impact Statement. The Station Operation Review Committee and the Company Nuclear Review Board have reviewed this LAR.
FPL Energy Seabrook requests NRC Staff review and approval of LAR 05-03 with issuance of a license amendment by March 31, 2006, and implementation of the amendment within 90 days.
an FPL Group company
U. S. Nuclear Regulatory Commission SBK-L05055 / Page 2 Should you have any questions regarding this letter, please contact Mr. James M. Peschel, Regulatory Programs Manager, at (603) 773-7194.
Very truly yours, FPL Energy Seabrook, LLC.
Mark E. Warner Site Vice President cc: S. J. Collins, NRC Region I Administrator V. Nerses, NRC Project Manager, Project Directorate I-2 G.T. Dentel, NRC Senior Resident Inspector Mr. Bruce Cheney, Director New Hampshire Office of Emergency Management State Office Park South 107 Pleasant Street Concord,NH 03301
FPL Energy Seabrook Station SEABROOK STATION UNIT 1 NPI?4 86pa 5 Dol;tNo.-5-443-, Z1-r,4* 1- d.,tRqi.,-.'. X03 n
- t v4;.>4$XYS.."Eem~ptiongfrom the End ofJ~ifeiMode'rator Tempertur Cofficient ;.;
The following information is enclosed in support of this License Amendment Request:
- Section I - Introduction and Safety Assessment for Proposed Change
- Section II - Markup of Proposed Change
- Section III - Retype of Proposed Change
- Section IV - Determination of Significant Hazards for Proposed Change
- Section V - Proposed Schedule for License Amendment Issuance And Effectiveness
- Section VI - Environmental Impact Assessment I, Mark E. Warner, Site Vice President of FPL Energy Seabrook, LLC hereby affirm that the information and statements contained within this License Amendment Request are based on facts and circumstances which are true and accurate to the best of my knowledge and belief.
Sworn and Subscribed before me this 9j day of Rarcl ,2005
/.----- flax Park E. Warner
_ Notary Pni..' %i--VicePresident
.2... E..
B.
I. INTRODUCTION AND SAFETY ASSESSMENT FOR PROPOSED CHANGE Introduction The proposed changes revise the near-end of life (EOL) moderator temperature coefficient (MTG) surveillance requirement (SR) 4.1.1.3.b by placing a set of conditions on core operation, which if met, would allow exemption from the required MTC measurement. The conditional exemption will be determined on a cycle-specific basis by considering the margin predicted to the surveillance requirement MTC limit and the performance of other core parameters, such as beginning of life (BOL) MTC measurements and critical boron concentration as a function of cycle length. The conditional exemption will improve plant availability and minimize disruptions to normal plant operation with no compromise in plant safety. This LAR requires no changes to the TS bases.
Proposed Changes
- 1. Technical Specification (TS) surveillance requirement 4.1.1.3 b is revised to suspend the MTC measurement if the model benchmark criteria and Revised Prediction specified in the Core Operating Limits Report (COLR) are satisfied.
- 2. The list of references for the COLR in TS 6.8.1.6.b. is revised to include WCAP-13749-P-A, "Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement."
Background
One of the controlling parameters for power and reactivity changes is the MTC. The requirements of TS 3.1.1.3 ensure that the MTC remains within the bounds used in the applicable Updated Final Safety Analysis Report (UFSAR) Chapter 15 accident analysis. This, in turn, ensures inherently stable power operations during normal operation and accident conditions.
TS 3.1.1.3, Moderator Temperature Coefficient, places limits on the MTC, based on the accident analysis assumptions for the moderator density coefficient. A positive moderator density coefficient corresponds to a negative MTC. TS 3.1.1.3 requires that the MTC be less negative than the specified limit for the all rods withdrawn, EOL, rated thermal power condition. To demonstrate compliance with the limiting condition for operation (LCO) for the most negative MTC, surveillance requirement 4.1.1.3.b requires verification of the MTC after reaching an equilibrium boron concentration of 300 ppm. Because the hot full power (HFP) MTC value will gradually become more negative with additional core bum up and boron concentration reduction, a 300 ppm MTC surveillance value should be less negative than the EOL LCO limit. To account for this effect, the 300 ppm MTC surveillance value is sufficiently less negative than the EOL LCO limit value to provide assurance that the LCO will be met as long as the 300 ppm MTC surveillance criterion is met.
1
Currently, the TS requires measurements of MTC at BOL to verify the most positive MTC limit and near EOL to verify the most negative MTC limit. At BOL, the measurement of the isothermal temperature coefficient is relatively simple to perform since it is done at hot zero power isothermal conditions and is not complicated by changes in the enthalpy rise or the presence of xenon. On the other hand, the measurement made near EOL is performed at or near HFP conditions. MTC measurements at HFP are more difficult to perform due to small variations in soluble boron concentration, changes in xenon concentration and distribution, changes in fuel temperature, and changes in enthalpy rise created by small changes in the core average power during the measurement.
Changes in each of these parameters must be accurately accounted for when reducing the measurement data or additional measurement uncertainties will be introduced. Even though these additional uncertainties may be small, the total reactivity change associated with the swing in moderator temperature induced to perform the surveillance test is also relatively small. The resulting MTC measurement uncertainty created by even a small change in power level may then become significant and, if improperly accounted for, can yield misleading measurement results.
Following the implementation of the Seabrook station power up-rate, the MTC measurement is expected to require several hours at reduced power to perform the test, introducing a perturbation to normal reactor operation. An alternate method is proposed to improve availability and minimize perturbations on normal reactor operation. The MTC measurement is replaced by a design calculation of the core MTC if predefined requirements are met. The proposed change modifies the EOL MTC surveillance requirement by placing a set of conditions on core operations. If these conditions are met, i.e., the specified revised prediction of the MTC and limits for several core parameters measured during the cycle are within specified bounds, performing the surveillance measurement is not required.
Safety Assessment of Proposed Changes The conditional exemption from the HFP near-EOL 300 ppm MTC measurement does not affect the safety analyses. The safety analyses assumption of a constant moderator density coefficient and the actual value assumed in the analyses will not change. The TS bases and limiting values for the most negative MTC are not altered. In lieu of performing the MTC measurement, SR 4.1.1.3.b is changed so that a revised predicted MTC is compared to the EOL MTC surveillance limit. If the revised predicted MTC is less negative than the EOL MTC surveillance limit, an MTC measurement is not required. The proposed method for calculating the revised predicted MTC is consistent with the approved methodology contained in WCAP-13749-P-A.
The methodology associated with the proposed change was submitted to the NRC in Westinghouse topical report WCAP-13749-P in June 1993. In October 1996, the NRC determined the topical report to be acceptable for referencing in license applications to the extent specified and under the limitations stated in the Brookhaven technical evaluation report and the NRC staffs Safety Evaluation Report (NRC letter: Acceptance for Referencing of Licensing Topical Report WCAP-3749-P, "Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL [End-of-Life] Moderator Temperature Coefficient Measurement", R. Jones (NRC) to N. Liparulo 2
(Westinghouse); October 9, 1996.)
The NRC approved WCAP-13749-P with two conditions:
- 1. Only PHOENIX/ANC calculation methods are used for the individual plant analyses relevant to determinations for the EOL MTC plant methodology, and
- 2. The predictive correction is reexamined if changes in core fuel designs or continued MTC calculation/measurement data show significant effect on the predictive correction.
FPL Energy Seabrook will meet both of these requirements. The PHOENIX-P/ANC calculation methods are used for the Seabrook Station core designs. Prior to each use of the conditional elimination technique, FPL Energy Seabrook will confirm that core design changes and MTC calculation and measurement data do not show a significant effect on the predictive correction. The administrative controls for this confirmation will reside in the Seabrook Station procedure that controls the EOL MTC surveillance. If a significant effect is found, the use of the predictive correction will be re-examined.
FPL Energy Seabrook is using NRC-approved WCAP-13749-P-A as the basis for this license amendment request and wvill meet the technical requirements (use of PHOENIX/ANC calculation methods, reexamination of the predictive correction if changes in core fuel designs or continued MTC calculation/measurement data show significant effect on the predictive correction, and adherence to the benchmarking criteria) in the approved WCAP. The core performance benchmark criteria, which are confirmed from startup physics test results, from routine HFP boron concentration measurements, and from flux map surveillances performed during the cycle, must be met before the revised predicted MTC can be calculated in accordance with the prescribed algorithm contained in WCAP-13749-P-A.
Appendix A of WCAP-1 3749-P-A requires a new Specification 6.9.1.7 to be added:
6.9.1.7 The most negative MTC limits shall be provided to the NRC Regional Administrator with a copy to the Director of Nuclear Reactor Regulation, Attention:
Chief, Core Performance Branch, U. S. Nuclear Regulatory Commission, Washington, D. C. 20555, at least 60 days prior to the date the limit would become effective unless otherwise approved by the Commission by letter. This report will include the data required for the determination of the Revised Prediction of the 300 ppm/ARO/RTP MTC per WCAP-13749, "Safety Evaluation Supporting the Conditional Elimination of the Most Negative EOL Moderator Temperature Coefficient Measurement", May, 1993 (Westinghouse Proprietary).
To reduce regulatory burden for both the NRC and the licensee, this LAR proposes not incorporating a "Most Negative Moderator Temperature Coefficient Limit Report" for two reasons. First, there is an inconsistency in WCAP-13749-P-A regarding the time frame of data collection and the submittal of the Most Negative Moderator Temperature Coefficient Limit Report to the NRC.
3
Additionally, the Most Negative Moderator Temperature Coefficient Limit Report serves no apparent technical purpose. Each of these reasons is discussed below.
Section 3.3.3 of WCAP-13749-P-A states:
"The Technical Specification Bases of the most negative MTC LCO and SR and the values of these limits are not altered. Instead, a revised prediction is compared to the SR MTC to determine if the SR limit is met. The revised prediction is simply the sum of the predicted HFP 300 ppm SR MTC plus an AFD correction factor plus a predictive correction term. This algorithm is summarized in Table 3-3."
Table D-2 of WCAP-13749-P-A, "Algorithm for Determining the Revised Predicted Near-EOL 300 PPM MTC," states:
"The Revised Predicted MTC = Predicted MTC + AFD Correction + Predicted Correction" Where:
"Predicted MTC is calculated from Figure 1 [Predicted HFP ARO 300 ppm MTC Versus Cycle Bum up] at the bum up corresponding to the measurement of 300 ppm at RTP conditions..."
Table D-3 of WCAP-13749-P-A provides an "Example Worksheet for Calculating the Revised Predicted Near-EOL 300 PPM MTC." Two of the required data inputs for this worksheet (B. I and B.2) are used to calculate the AFD correction term in the algorithm:
B.1 Bum up of most recent HFP, equilibrium MWD/MTU conditions incore flux map B.2 Measured HFP AFD at bum up (B.1) % AFD Reference incore flux map I.D. Date:
Since the Most Negative Moderator Temperature Coefficient Limit Report would have to be submitted at least 60 days before reaching 300 ppm boron concentration, it cannot include the 300 ppm data required for determining the Revised Prediction. To satisfy the Most Negative Moderator Temperature Coefficient Limit Report submittal requirement, the hot full power AFD data to be used for calculating the revised predicted MTC may have to be taken 60 to 90 days prior to reaching 300 ppm boron. WCAP-13749-P-A neither provides any method for adjusting the revised predicted 4
MTC to account for data collected 60 to 90 days prior to 300 ppm nor does it provide justification for using such early data in the calculation. Therefore, the requirement to submit the Most Negative Moderator Temperature Coefficient Limit Report and the requirements for the data that go into the report are inconsistent.
Additionally, the Most Negative Moderator Temperature Coefficient Limit Report serves no apparent technical requirement. The applicabilityrestrictions contained in WCAP-13749-P-A, the algorithm, and the data required for determining the Revised Prediction will be included in Seabrook Station procedures governing the EOL MTC surveillance. There is no compelling reason that this particular surveillance should require notifying the NRC prior to performing the surveillance procedure. An exception to the requirement for a "Most Negative Moderator Temperature Coefficient Limit Report" was approved by the NRC for South Texas Units 1 and 2 in Amendment 144 to Facility Operating License No. NPF-76 and Amendment 132 to Facility Operating License No. NPF-80 on November 26, 2002.
The fourth paragraph in Section 3.2.1 of WCAP-13749-P-A states: "As part of determining the applicability of a conditional exemption from the near-EOC MTC measurement, a cycle-specific figure similar to Figure 3-1 will be provided as part of that cycle's Technical Specifications or Core Operating Limits Report (COLR). This approach..." However, the COLR changes contained in Appendix B, "COLR Revision," of WCAP-13749-P-A do not include a reference to Figure 3-1, Example of Predicted HFP ARO 300 ppm MTC Versus Cycle Burn Up. As a result, LAR 05-03 proposes including the appropriate cycle specific figure (predicted HFP ARO 300 ppm MTC versus cycle burn up) for Seabrook and the benchmark criteria in the surveillance procedure for the EOL MTC measurement. The COLR will contain the algorithm for the Revised Predicted MTC similar to the draft change to the COLR shown in attachment A.
5
SECTION II MARKUP OF PROPOSED CHANGE Refer to the attached markup of the proposed change to the Technical Specifications. The attached markup reflects the currently issued revision of the Technical Specifications listed below. Pending Technical Specifications or Technical Specification changes issued subsequent to this submittal are not reflected in the enclosed markup.
The following Technical Specifications are included in the attached markup:
Technical Specification Title Page 4.1.1.3 Moderator Temperature Coefficient 3/4 1-5 6.8. 1.6.b Core Operating Limits Report 6-18E
REACTIVITY CONTROL SYSTEMS BORATION CONTROL MODERATOR TEMPERATURE COEFFICIENT SURVEILLANCE REQUIREMENTS 4.1.1.3 The MTC shall be determined to be within its limits during each fuel cycle as follows:
- a. The MTC shall be measured and compared to the BOL limit specified in the COLR, prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading; and
- b. The MTC shall be measured at any THERMAL POWER and compared to the 300 ppm surveillance limit specified in the COLR (all rods withdrawn, RATED
.-.. ~ THERMAL POWER condition) within 7 EFPD after reaching an equilibrium boron concentration of 300 ppm. Inthe event this comparison indicates the MTC is more negative than the 300 ppm surveillance limit specified in the COLR, the MTC shall be remeasured, and compared to the EOL MTC limit specified in the COLR, at least once per 14 EFPD during the remainder of the fuel cycle.
SEABROOK - UNIT 1 3/4 1-5 Amendment No.+9
INSERT 1
ADMINISTRATIVE CONTROLS 6.8.1 .6.b. (Continued)
- 15. WCAP-9272-P-A, (Proprietary), "Westinghouse Reload Safety Evaluation Methodology", July, 1985.
Methodology for Specifications:
2.1 - Safety Limits 3.1.1.1 - SHUTDOWN MARGIN for MODES 1,2,3, and 4 3.1.1.2 - SHUTDOWN MARGIN for MODE 5 3.1.1.3 - Moderator Temperature Coefficient 3.1.2.7 - Isolation of Unborated Water Sources - Shutdown 3.1.3.5 - Shutdown Rod Insertion Limit 3.1.3.6 - Control Rod Insertion Limits 3.2.1 - AXIAL FLUX DIFFERENCE 3.2.2 - Heat Flux Hot Channel Factor 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor 3.2.5 - DNB Parameters 3.5.1.1 - Accumulators for MODES 1, 2 and 3 3.5.4 - Refueling Water Storage Tank for MODES 1, 2, 3, and 4 3.9.1 - Boron Concentration I 1;1 6.8.1 .6.c. The core operating limits shall be determined so that all applicable limits (e.g.,
fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as SHUTDOWN MARGIN, and transient and accident analysis limits) of the safety analysis are met. The CORE OPERATING LIMITS REPORT for each reload cycle, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, to the NRC Document Control Desk with copies to the Regional Administrator and the Resident Inspector.
SEABROOK - UNIT 1 6-1 8E Amendment No. -76, INSERT 2
- 16. WCAP-13749-P-A, (Proprietary) "Safety Evaluation Supporting the Conditional Exemption of the Most Negative Moderator Temperature Coefficient Measurement,"
March 1997 Methodology for Specification:
3.1.1.3 - Moderator Temperature Coefficient
SECTION III RETYPE OF PROPOSED CHANGE Refer to the attached retype of the proposed change to the Technical Specifications. The attached retype reflects the currently issued version of the Technical Specifications. Pending Technical Specification changes or Technical Specification changes issued subsequent to this submittal are not reflected in the enclosed retype. The enclosed retype should be checked for continuity with Technical Specifications prior to issuance.
The following Technical Specifications are included in the attached retype:
Technical Specification Title Page 4.1.1.3 Moderator Temperature Coefficient 3/4 1-5 6.8.1 .6.b Core Operating Limits Report 6-18E
REACTIVITY CONTROL SYSTEMS BORATION CONTROL MODERATOR TEMPERATURE COEFFICIENT SURVEILLANCE REQUIREMENTS 4.1.1.3 The MTC shall be determined to be within its limits during each fuel cycle as follows:
- a. The MTC shall be measured and compared to the BOL limit specified in the COLR, prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading; and
- b. The MTC shall be measured at any THERMAL POWER and compared to the 300 ppm surveillance limit specified in the COLR (all rods withdrawn, RATED THERMAL POWER condition) within 7 EFPD after reaching an equilibrium boron concentration of 300 ppm*. In the event this comparison indicates the MTC is more I negative than the 300 ppm surveillance limit specified in the COLR, the MTC shall be remeasured, and compared to the EOL MTC limit specified in the COLR, at least once per 14 EFPD during the remainder of the fuel cycle.
- Measurement of the MTC in accordance with Surveillance Requirement 4.1.1.3.b may be suspended provided that the benchmark criteria in WCAP-1 3749-P-A and the Revised Prediction specified in the COLR are satisfied.
SEABROOK - UNIT 1 3/4 1-5 Amendment No. 0
ADMINISTRATIVE CONTROLS 6.8.1 .6.b. (Continued)
- 15. WCAP-9272-P-A, (Proprietary), "Westinghouse Reload Safety Evaluation Methodology", July, 1985.
Methodology for Specifications:
2.1 - Safety Limits 3.1.1.1 - SHUTDOWN MARGIN for MODES 1,2,3, and 4 3.1.1.2 - SHUTDOWN MARGIN for MODE 5 3.1.1.3 - Moderator Temperature Coefficient 3.1.2.7 - Isolation of Unborated Water Sources - Shutdown 3.1.3.5 - Shutdown Rod Insertion Limit 3.1.3.6 - Control Rod Insertion Limits 3.2.1 - AXIAL FLUX DIFFERENCE 3.2.2 - Heat Flux Hot Channel Factor 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor 3.2.5 - DNB Parameters 3.5.1.1 - Accumulators for MODES 1, 2 and 3 3.5.4 - Refueling Water Storage Tank for MODES 1, 2, 3, and 4 3.9.1 - Boron Concentration
- 16. WCAP-13749-P-A, (Proprietary) "Safety Evaluation Supporting the Conditional Exemption of the Most Negative Moderator Temperature Coefficient Measurement", March, 1997.
Methodology for Specifications:
3.1.1.3 - Moderator Temperature Coefficient 6.8.1 .6.c. The core operating limits shall be determined so that all applicable limits (e.g.,
fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as SHUTDOWN MARGIN, and transient and accident analysis limits) of the safety analysis are met. The CORE OPERATING LIMITS REPORT for each reload cycle, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, to the NRC Document Control Desk with copies to the Regional Administrator and the Resident Inspector.
SEABROOK - UNIT 1 6-1 8E Amendment No. 276,06
IV. DETERMINATION OF SIGNIFICANT HAZARDS FOR PROPOSED CHANGE In accordance with 10 CFR 50.92, FPL Energy Seabrook has concluded that the proposed changes do not involve a significant hazards consideration (SHC). The basis for the conclusion that the proposed changes do not involve a SHC is as follows:
- 1. The proposed changes do not involve a significant increase in the probability or consequences of an accidentpreviously evaluated.
The probability or consequences of accidents previously evaluated in the UFSAR are unaffected by this proposed change. There is no change to any equipment response or accident mitigation scenario, and this change results in no additional challenges to fission product barrier integrity. The proposed change does not alter the design, configuration, operation, or function of any plant system, structure, or component. Further, the existing limits on moderator temperature coefficient (MTC) established by the Technical Specifications (TS), based on assumptions in the safety analyses, remain unchanged and continue to be satisfied. As a result, the outcomes of previously evaluated accidents are unaffected. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. The proposed changes do not create the possibility of a new or different kind of accident fromn any previously evaluated.
No new accident scenarios, failure mechanisms, or limiting single failures are introduced as a result of the proposed change. The proposed change does not challenge the performance or integrity of any safety-related system. The proposed change neither installs or removes any plant equipment, nor alters the design, physical configuration, or mode of operation of any plant structure, system, or component. The MTC is a variable that must remain within prescribed limits, but it is not an accident initiator. No physical changes are being made to the plant, so no new accident causal mechanisms are being introduced. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. The proposed changes do not involve a significant reduction in the margin of safety.
The margin of safety associated with the acceptance criteria of any accident is unchanged.
The proposed change will have no affect on the availability, operability, or performance of the safety-related systems and components. The proposed change does not alter the design, configuration, operation, or function of any plant system, structure, or component.
The ability of any operable structure, system, or component to perform its designated safety function is unaffected by this change. A change to a surveillance requirement is proposed based on an alternate method of confirming that the surveillance is met.
The Technical Specifications establish limits for the moderator temperature coefficient (MTC) based on assumptions in the accident analyses. Applying the conditional exemption from the MTC measurement changes the method of meeting the surveillance requirement; however, this change does not modify the TS values and ensures adherence to the current TS limits. The basis for the derivation of the MTC limits from the moderator density coefficient (MDC) assumed in the accident analysis is unchanged.
Further, the safety analysis assumption of a constant MDC and its assumed value will not change. Therefore, the margin of safety as defined in the TS is not reduced and the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, FPL Energy Seabrook has determined that the proposed amendment does not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any previously evaluated, or (3) involve a significant reduction in the margin of safety.
Consequently, this proposed change does not involve a significant hazards consideration.
V. PROPOSED SCHEDULE FOR LICENSE AMENDMENT ISSUANCE AND EFFECTIVENESS FPL Energy Seabrook requests NRC review of License Amendment Request 05-03, and issuance of a license amendment by March 31, 2006, having immediate effectiveness and implementation within 90 days.
VI. ENVIRONMENTAL IMPACT ASSESSMENT FPL Energy Seabrook has reviewed the proposed license amendment against the criteria of 10 CFR 51.22 for environmental considerations. The proposed changes do not involve a significant hazards consideration, nor increase the types and amounts of effluent that may be released offsite, nor significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, FPL Energy Seabrook concludes that the proposed changes meet the criteria delineated in 10 CFR 51.22(c)(9) for a categorical exclusion from the requirements for an Environmental Impact Statement.
ATTACHMENT A Draft Change to the COLR
2.5 Moderator Temperature Coefficient: (Specification 3.1.1.3) 2.5.1 The Moderator Temperature Coefficient (MTC) shall be less positive than
+3.12 x 10-5 AK/K/ 0F for Beginning of Cycle Life (BOL), All Rods Out (ARO), Hot Zero Thermal Power conditions.
2.5.2 MTC shall be less negative than -5.0 x 104 AK/K/OF for End of Cycle Life (EOL), ARO, Rated Thermal Power conditions.
2.5.3 The 300 ppm ARO, Rated Thermal Power MTC shall be less negative than -4.1 x 10 4 AK/K/OF (300 ppm Surveillance Limit).
2.5.4 The Revised Predicted near-EOL 300 ppm MTC shall be calculated using the algorithm contained in WCAP 13749-P-A:
Revised Predicted MTC = Predicted MTC + AFD Correction - 3 PCMI degree F If the Revised Predicted MTC is less negative than the SR 4.1.1.3.b 300 ppm surveillance limit and all the benchmark data contained in the surveillance procedure are met, then an MTC measurement in accordance with SR 4.1.1.3.b is not required to be performed.