|
---|
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
[Table view] |
Text
NEXTera ENERGY
',,0 ý EAROK July 14, 2011 10 CFR 50.90 SBK-L-1 1130 Docket No. 50-443 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Seabrook Station License Amendment Request 11-03 License Amendment Request Regarding Containment Spray Nozzles Surveillance Requirement In accordance with the provisions of Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), NextEra Energy Seabrook, LLC (NextEra) is submitting License Amendment Request (LAR) 11-03 for an amendment to the Technical Specifications (TS) for Seabrook Station. The proposed change replaces the ten-year surveillance frequency for testing the containment spray nozzles in accordance with TS surveillance 4.6.2.1 .d with an event-based frequency.
Attachment 1 to this letter provides NextEra's evaluation of the proposed change, and Attachment 2 provides a markup of the TS showing the proposed change. New TS pages with the proposed change incorporated will be provided when requested by the NRC Project Manager.
Associated TS Bases changes will be implemented in accordance with TS 6.7.6j, TS Bases Control Program, upon implementation of the license amendment. As discussed in the evaluation, the proposed change does not involve a significant hazards consideration pursuant to 10 CFR 50.92, and there are no significant environmental impacts associated with the change.
No new commitments are made as a result of this change.
The Station Operation Review Committee has reviewed this LAR. A copy of this LAR has been forwarded to the New Hampshire State Liaison Officer pursuant to 10 CFR 50.91(b).
NextEra requests NRC review and approval of LAR 11-03 with issuance of a license amendment by July 15, 2012 and implementation of the amendment within 90 days.
NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874
United States Nuclear Regulatory Commission SBK-L-11130 / Page 2 Should you have any questions regarding this letter, please contact Mr. Michael O'Keefe, Licensing Manager, at (603) 773-7745.
Sincerely, NextEra Energy Seabrook, LLC Paul Freeman Site Vice President Attachments
- 1. NextEra Energy Seabrook's Evaluation of the Proposed Change
- 2. Markup of the Technical Specifications cc: NRC Region I Administrator G. E. Miller, NRC Project Manager W. J. Raymond, NRC Senior Resident Inspector Mr. Christopher M. Pope, Director Homeland Security and Emergency Management New Hampshire Department of Safety Division of Homeland Security and Emergency Management Bureau of Emergency Management 33 Hazen Drive Concord, NH 03305 Mr. John Giarrusso, Jr., Nuclear Preparedness Manager The Commonwealth of Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399
ENERY SEABROOK AFFIDAVIT SEABROOK STATION UNIT 1 Facility Operating License NPF-86 Docket No. 50-443 License Amendment Request 11-03 License'AmendmentRequest Regarding Containment Spray Nozzles Surveillance Requirement The following information is enclosed in support of this License Amendment Request:
S NextEra Energy Seabrook's Evaluation of the Proposed Change 0 Markup of the Technical Specifications I, Paul Freeman, Site Vice President of NextEra 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
- beforeme this 1 dayof 2011 K~*zzI~
Paul Freeman Notary Pblic Site Vice President
Attachment 1 NextEra Energy Seabrook's Evaluation of the Proposed Change
Subject:
License Amendment Request Regarding Containment Spray Nozzles Surveillance Requirement 1.0
SUMMARY
DESCRIPTION 2.0 DETAILED DESCRIPTION
3.0 TECHNICAL EVALUATION
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria 4.2 Precedent 4.3 Significant Hazards Consideration 4.4 Conclusion
5.0 ENVIRONMENTAL CONSIDERATION
6.0 REFERENCES
1
1.0
SUMMARY
DESCRIPTION The proposed change revises the Technical Specifications (TS) for the containment building spray (CBS) system. Current surveillance requirement (SR) 4.6.2.1 .d requires performing an air or smoke test through each containment spray header and verifying each spray nozzle is unobstructed at least once every ten years. NextEra proposes to replace the fixed ten-year interval with an event based frequency.
2.0 DETAILED DESCRIPTION The proposed change revises SR 4.6.2.1 .d as shown below:
- d. At least once per-10 years by per-fomin an ai Or SMoke flow test through each spr.ay header-and verifing each spray nozzle is unobstr*eted. By verifying each spray nozzle is unobstructedfollowing activities that could result in nozzle blockage.
Attachment 2 provides the TS page marked to show the proposed change.
3.0 TECHNICAL EVALUATION
Background
Description of Containment Building Spray System [Reference 1]
The containment is maintained below design pressure following a primary or secondary system line rupture by the parallel action of the emergency core cooling system (ECCS) and the CBS system, which comprise the containment heat removal system discussed in the Seabrook Updated Final Safety Analysis Report. The CBS system is designed to remove the energy discharged to the containment following a loss of coolant accident or main steam line break to prevent the containment pressure from exceeding design pressure and to reduce and maintain containment temperature and pressure within acceptable limits. The ECCS system and CBS system are comprised of two identical trains, each train independent of the other and fully redundant. Failure of a single active component will not cause the loss of more than half of either system's 200 percent heat removal capacity.
The CBS system is comprised of the CBS pumps, heat exchangers, spray headers and nozzles, the refueling water storage tank (RWST), the spray additive tank (SAT), and the containment recirculation sumps along with the interconnecting piping and valves and associated instrumentation and controls. The CBS spray headers and nozzles are positioned in the containment dome to maximize coverage of the containment volume. Four separate headers (two for each train) are utilized to obtain distribution 2
of the flow. Each train contains 198 nozzles with each nozzle providing a design flow of 15.2 gallons per minute. The containment spray headers and nozzles are fabricated of Austenitic stainless steel.
The CBS system is actuated by a containment spray actuation signal, which is initiated by high pressure in the containment. The CBS system pumps deliver water from the RWST to the spray nozzles located high in the containment building.
Through out the injection phase, the CBS pumps deliver water from the RWST through the CBS heat exchangers to the spray nozzles in containment. A low-low level signal from the RWST initiates the recirculation mode of operation, and the suctions of the residual heat removal (RHR) and the CBS pumps automatically re-align to the containment recirculation sumps. Throughout the recirculation mode, the CBS pumps take suction from the water in the containment recirculation sumps and discharge through the CBS heat exchangers to the containment spray nozzles and into the containment.
Conditions the Proposed Change is Intended to Resolve This proposed change will eliminate unnecessary testing of spray nozzles by requiring the test be performed following activities or conditions that could potentially cause nozzle blockage. The current surveillance requires workers to verify air flow at each nozzle located at high elevations inside containment, and the proposed reduction in the frequency of testing will enhance personnel safety.
Additionally, the surveillance also requires the use of a compressor with high temperature output and the installation of high temperature hoses. Reduction in the use of the high temperature compressor and hoses would also enhance personnel safety. Similarly, the proposed change is expected to result in a reduction in personnel radiation exposure and outage costs associated with performing the test.
Evaluation The proposed change will allow testing for nozzle blockage based on the occurrence of activities that could cause nozzle blockage rather than a fixed periodic basis. This change is requested based on industry and plant experience that indicates blockage of the containment spray nozzles during normal plant operation is unlikely.
PerformanceHistory Preoperational testing of the CBS system verified the operational parameters of the spray pumps during recirculation to the RWST. This testing included a demonstration of the system response to engineered safety features signals and the ability of the sump to supply the CBS and RHR pumps. Flow testing of the nozzles 3
was performed by the manufacturer and was not performed in the field. An air flow test was performed to verify that no nozzles were plugged.
Periodic in-place air flow tests through the spray nozzles have been conducted at the interval specified in the TS. The air flow test is performed by removing a piping spool piece from the pipe riser to the ring header and connecting an external air source that supplies hot air (approximately 325 0 F) and verifying that each spray nozzle is not plugged using a thermography camera.
The containment spray nozzle test history is as follows:
" Test 1 Performed as part of preoperational test in 1986.
- Test 2 Performed on 8/21/1991 during refueling outage 1.
" Test 3 Performed on 5/12/2002 during refueling outage 8.
The results of each test demonstrated unobstructed flow through each nozzle. These tests confirmed that the systems were free from construction debris and that no debris that could have caused obstructions had entered the system following startup and operation of Seabrook Station.
Nozzle Blockage Mechanisms NUREG-1366, "Improvements to Technical Specifications Surveillance Requirements," [Reference 2] reported the results of an NRC staff review of industry experience related to problems with CBS systems. The report found that, in general, once the systems are tested after construction, they are not subject to blockage. The problems regarding nozzle blockage identified in the report were related to construction activities.
One postulated mechanism for blockage of spray nozzles is corrosion products. The containment spray headers and nozzles, however, are fabricated of Austenitic stainless steel. Therefore, blockage of the spray nozzles from corrosion products is unlikely.
Another mechanism for nozzle blockage is accumulation of solid boric acid in the spray lines or nozzles due to evaporated borated water. The CBS spray headers are normally maintained dry and isolated from water by normally closed containment isolation valves that are subject to Type C leakage testing. During refueling outages, the spray ring manual isolation valves are locked closed to ensure that inadvertent spray actuation cannot take place. As a further means to prevent materials from entering the system, the containment sumps may have covers installed.
Consequently, blockage of the CBS spray nozzles from solid boric acid accumulation 4
is unlikely. However, should there be inadvertent fluid flow though the nozzles, such as the result of spurious actuation, NextEra would evaluate testing and methods for verifying the nozzles are unobstructed.
ForeignMaterialExclusion (FME)
The FME program at Seabrook Station is governed by Fleet Procedure MA-AA-101-1000. This procedure ensures that appropriate precautions are taken to minimize inadvertent and uncontrolled introduction of foreign materials into plant systems and components. Breached fluid or piping systems shall be covered where possible except when the specific opening is attended or work, inspection, testing, sampling, or surveying is in progress that requires the removal of the FME cover. The procedure also includes FME practices for maintaining cleanliness of plant systems and components during maintenance activities that create debris, such as welding and grinding. Final cleanliness inspections verify the system, component, or process is free of foreign material prior to final closure.
NextEra's corrective action process is used in the event of a loss of FME integrity. If FME integrity is lost through the intrusion or discovery of foreign material, the procedure directs the worker to notify the work group supervisor or designee to develop a recovery plan for the foreign material. The recovery plan should include the following considerations: methods to save recovered materials for further analysis, determination of the source, location, and quantity of foreign material; determination of the need for additional inspections, and evaluation of possible equipment damage already caused or that may be caused by the foreign material.
NextEra performed a review of maintenance performed on the CBS system since the last containment spray nozzle test in refueling outage 8 in May 2002. The review identified one issue involving FME that impacted the CBS system. During installation of a new vent valve (CBS-V-178), the purge dam pipe became detached from the argon hose and fell into the piping. This issue was documented in the corrective action program; and in accordance with the FME program, a recovery plan was developed, the purge dam pipe was retrieved, and an internal FME inspection was performed. Identification of the FME issue, development of a recovery plan, and successful retrieval of the purge dam pipe indicate that NextEra has an effective FME program.
During other maintenance activities on the CBS system since the last containment spray nozzles test, work practices and post work inspections maintained system cleanliness. There have been no work activities on any of the containment spray nozzles or headers since the last containment spray nozzle test.
NextEra's administrative controls for FME ensure that foreign material is excluded from systems during maintenance activities, and these controls would be in place with 5
the CBS system open for maintenance. Therefore, the FME program provides reasonable assurance that debris or foreign matter that could adversely affect the CBS system's ability to perform its safety function would not be left in the system as a result of maintenance activities.
Conclusion The NRC has recognized that CBS nozzle testing on a ten-year frequency is unnecessary. NUREG-1366 found that problems in pressurized water reactor CBS systems were generally related to construction activities. Previously performed surveillance tests all found the Seabrook Station CBS nozzles unobstructed, and a reduced frequency of testing is justified when experience has shown routine testing at a specified frequency produces acceptable results. The design of the CBS system, maintenance and testing history of the system, and robust FME controls provide reasonable assurance that the reduced surveillance frequency will not impact the ability of the CBS system to perform its specified function.
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria 0 10 CFR 50.36, Technical Specifications, states (c) Technical specifications will include items in the following categories:
(3) Surveillance requirements.Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.
- General Design Criterion 38--Containmentheat removal. A system to remove heat from the reactor containment shall be provided. The system safety function shall be to reduce rapidly, consistent with the functioning of other associated systems, the containment pressure and temperature following any loss-of-coolant accident and maintain them at acceptably low levels.
- GeneralDesign Criterion39--Inspection of containment heat removal system. The containment heat removal system shall be designed to permit appropriate periodic inspection of important components, such as the torus, sumps, spray nozzles, and piping to assure the integrity and capability of the system.
6
Criterion 40--Testing of containment heat removal system. The containment heat removal system shall be designed to permit appropriate periodic pressure and functional testing to assure (1) the structural and leaktight integrity of its components, (2) the operability and performance of the active components of the system, and (3) the operability of the system as a whole, and under conditions as close to the design as practical the performance of the full operational sequence that brings the system into operation, including operation of applicable portions of the protection system, the transfer between normal and emergency power sources, and the operation of the associated cooling water system.
The changes proposed in this request will continue to meet the above regulatory requirements.
4.2 Precedent The NRC staff has approved similar license amendments including:
- Catawba, McGuire, and Oconee Stations (August 24, 2010; ADAMS Accession No. ML100690007) [Reference 3]
- Prairie Island Units, 1 and 2 (November 6, 2008; ADAMS Accession No.ML082740226) [Reference 4]
" Millstone Power Station, Unit 2 (March 31, 2008; ADAMS Accession No. ML080720304) [Reference 5]
" Arkansas Nuclear One Unit 1 (July 9, 2008; ADAMS Accession No. ML081540218) [Reference 6]
4.3 Significant Hazards Consideration No Significant Hazards Consideration In accordance with 10 CFR 50.92, NextEra Energy Seabrook has concluded that the proposed change does not involve a significant hazards consideration (SHC). The basis for the conclusion that the proposed change does not involve a SHC is as follows:
- 1. The proposed change does not involve a significant increase in the probabilityor consequences of an accidentpreviously evaluated.
7
The spray nozzles and the associated containment spray system (CBS) are designed to perform accident mitigation functions. The proposed change to reduce the frequency and remove specific details of surveillance testing that verifies the spray nozzles are unobstructed does not impact the physical function of plant structures, systems, or components (SSCs) or the manner in which SSCs perform their design function. The proposed change neither adversely affects accident initiators or precursors, nor alters design assumptions. The proposed change does not alter or prevent the ability of operable SSCs to perform their intended function to mitigate the consequences of an initiating event within assumed acceptance limits.
The capability of the CBS system to perform its accident mitigation functions is not adversely affected by the proposed change.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. The proposed change does not create the possibility of a new or different kind of accidentfrom any previously evaluated.
The proposed change will not impact the accident analysis. The change does not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed), a significant change in the method of plant operation, or new operator actions. The change does not make any physical modifications to the CBS system, changes to setpoints, or changes to the method of delivering borated water to the CBS spray nozzles. The proposed change will not introduce failure modes that could result in a new accident, and the change does not alter assumptions made in the safety analysis.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. The proposed change does not involve a significant reduction in the margin of safety.
Margin of safety is associated with confidence in the ability of the fission product barriers (i.e., fuel cladding, reactor coolant system pressure boundary, and containment structure) to limit the level of radiation dose to the public. The proposed change does not involve a significant change in the method of plant operation, and no accident analyses will be affected by the proposed changes. Additionally, the proposed changes will not relax any criteria used to establish safety limits and will not relax any safety system settings. The safety analysis acceptance criteria are not affected by this change. The proposed change will not result in plant operation in a configuration outside the design basis. The proposed change does not 8
adversely affect systems that respond to safely shutdown the plant and to maintain the plant in a safe shutdown condition.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, NextEra concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(b), and, accordingly, a finding of"no significant hazards consideration" is justified.
4.3 Conclusions Based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
5.0 ENVIRONMENTAL CONSIDERATION
NextEra has evaluated the proposed amendment for environmental considerations.
The review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set for in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the proposed amendment.
9
6.0 REFERENCES
- 1. Seabrook Station UFSAR, Revision 14, section 6.2.2
- 2. NUREG-1366, "Improvements to Technical Specifications Surveillance Requirements," December, 1992
- 3. NRC letter "Catawba Nuclear Station, Units 1 and 2, McGuire Nuclear Station, Units 1 and 2, and Oconee Nuclear Station, Units 1, 2, and 3, Issuance of Amendments Regarding Performance Testing of Containment Spray Nozzles (TAC Nos. ME2497, ME 2498, ME2499, ME2500, ME2501, ME2502 and ME2503)," August 24, 2010, ADAMS Accession ML100690007
- 4. NRC letter "Prairie Island Nuclear Generating Plant, Units I and 2 - Issuance of Amendments Re: License Amendment to Revise Containment Spray Nozzle Surveillance Requirements (TAC Nos. MD7362 and MD7363)," November 6, 2008, ADAMS Accession ML082740226
- 5. NRC letter "Millstone Power Station, Unit 2 - Issuance of Amendment Re:
Technical Specification Change Request Regarding Containment Spray Nozzle Test Requirements (TAC No. MD4992)," March 31, 2008, ADAMS Accession 080720301
- 6. NRC letter "Arkansas Nuclear One, Unit 1 - Issuance of Amendment Re:
Containment Spray Nozzle Technical Specifications Test Requirements (TAC No. MD83 10)," July 9, 2008, ADAMS Accession ML081540218 10
Attachment 2 Mark-up of the Technical Specifications (TS)
The attached markup reflects the currently issued version of the TS and Facility Operating License. At the time of submittal, the Facility Operating License was revised through Amendment No. 125.
Listed below are the license amendment requests that are awaiting NRC approval and may impact the currently issued version of the Facility Operating License affected by this LAR.
LAR 'Title NextEra Energy Date Seabrook Letter Submitted LAR 10-02 Application for Change to the SBK-L-10074 05/14/2010 Technical Specifications for the Containment Enclosure Emergency Air Cleanup System LAR 10-04 Amendment to the Facility SBK-L-101 19 07/26/2010 Operating License and Submittal of the Seabrook Station Cyber Security Plan LAR 10-05 Application to Delete Technical SBK-L-10153 12/29/2010 Specification 3/4.4.10, Structural Integrity.
Application to Revise the Technical SBK-L-1 1066 04/21/2011 LAR 11-01 Specifications for Reactor Coolant Leakage Detection Instrumentation The following TS page is included in the attached markup:
Technical Title Page Specification TS 3.6.2.1 Containment Spray System 3/4 6-14 I
CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent Containment Spray Systems shall be OPERABLE with each Spray System capable of taking suction from the RWST* and automatically transferring suction to the containment sump.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With one Containment Spray System inoperable, restore the inoperable Spray System to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the inoperable Spray System to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.1 Each Containment Spray System shall be demonstrated OPERABLE:
- a. At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position;
- b. By verifying OPERABILITY of each pump when tested pursuant to Specification 4.0.5;
- c. At least once per 18 months during shutdown, by:
- 1) Verifying that each automatic valve in the flow path actuates to its correct position on a Containment Pressure-Hi-3 test signal, and
- 2) Verifying that each spray pump starts automatically on a Containment Pressure-Hi-3 test signal.
- d. aAt leas,%t.eýe perjqye9'r S b y pe rf qjxF4ri an,ýaaýir- o e flow 1pa4tm h c sprayc:4 e-Ach besTerý1 and verifýnýeach sprayý ozzle pfray:ý:e:ra:n ozz, iss u, ed uneb-sTr-ucted.
- In MCDE 4, when the Residual Heat Removal System is in operation, ann'oa OPERABLE ow ctERABLugEnIflow path i one that is capable of taking suction from the refueling water storage s Ptank 0 ta n k upon up being manually realigned.
SEABFROOK - UNIT 1 3/46-14 Amendment geru 0w No. 30,4ý9_
ve, / '5ý4evyl
- dozz-le- AS 411-lazzrl *We/go 11*ý 0ý7