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TAC:ME3988, Ventilation System Envelope Allowed Outage Time (Approved, Closed) |
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MONTHYEARSBK-L-10074, License Amendment Request 10-022010-05-14014 May 2010 License Amendment Request 10-02 Project stage: Request ML1016605532010-06-15015 June 2010 E-mail, Miller, to O'Keefe, Seabrook Acceptance Review LAR 10-02 Ceeacs LCO Project stage: Acceptance Review ML1021800132010-08-0505 August 2010 Electronic Transmission, Draft Request for Additional Information Regarding License Amendment Request Related to Containment Emergency Air Cleanup System Project stage: Draft RAI ML1122101392011-08-10010 August 2011 Electronic Transmission, Draft Request for Additional Information Regarding License Amendment Request 10-02 Regarding the Containment Enclosure Emergency Air Cleanup System Project stage: Draft RAI SBK-L-11184, Response to Request for Additional Information Regarding License Amendment Request 10-02, Regarding the Containment Enclosure Emergency Air Cleanup System2011-09-16016 September 2011 Response to Request for Additional Information Regarding License Amendment Request 10-02, Regarding the Containment Enclosure Emergency Air Cleanup System Project stage: Response to RAI SBK-L-12054, Response to Request for Additional Information Regarding License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System2012-03-15015 March 2012 Response to Request for Additional Information Regarding License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System Project stage: Response to RAI ML12156A2892012-06-11011 June 2012 Request for Additional Information Regarding the Addition of Action Statement to Limiting Condition for Operation 3.6.5.1, Containment Enclosure Emergency Air Cleanup System Project stage: RAI 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 Project stage: Supplement 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 Project stage: Approval ML13114A3172013-04-25025 April 2013 Correction to Issuance of Amendment 136 Addition of Action Statement to Limiting Condition for Operation 3.6.5.1, Containment Enclosure Emergency Air Cleanup System Project stage: Approval 2011-09-16
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Category:Letter
MONTHYEARIR 05000443/20244022024-10-17017 October 2024 Material Control and Accounting Program Inspection Report 05000443/2024402 (Cover Letter Only) L-2024-159, Core Operating Limits Report for Reload Cycle 242024-10-15015 October 2024 Core Operating Limits Report for Reload Cycle 24 ML24254A2552024-09-25025 September 2024 Alternative Request No. 4A-01 for the Fourth 10-Year Inservice Inspection Interval L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24239A5382024-09-20020 September 2024 Issuance of Amendment No. 175 One-Time Allowable Outage Time Extension to the Technical Specification 3.8.1.1, A.C. Sources – Operating, Limiting Condition for Operation L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000443/20240052024-08-29029 August 2024 Updated Inspection Plan for Seabrook Station (Report 05000443/2024005) ML24232A1142024-08-21021 August 2024 Correction to Amendment No. 174 to Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (LTOP) Curves L-2024-141, Third Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit2024-08-15015 August 2024 Third Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Be L-2024-137, Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent .2024-08-12012 August 2024 Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent . IR 05000443/20240022024-08-0606 August 2024 Integrated Inspection Report 05000443/2024002 and Independent Spent Fuel Storage Installation Inspection Report 07200063/2024001 L-2024-127, Supplement to Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent2024-08-0505 August 2024 Supplement to Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite.2024-07-16016 July 2024 Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite. ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-098, Preparation and Scheduling of Operator Licensing Examinations2024-06-12012 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-084, Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld2024-05-30030 May 2024 Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld IR 05000443/20240102024-05-29029 May 2024 Biennial Problem Identification and Resolution Inspection Report 05000443/2024010 IR 05000443/20240112024-05-24024 May 2024 Age-Related Degradation Inspection Report 05000443/2024011 IR 05000443/20240012024-05-13013 May 2024 Integrated Inspection Report 05000443/2024001 L-2024-061, NextEra Energy Seabrook, LLC, License Amendment Request - One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite Transmission Network and the Onsite Class 1E Distribut2024-05-10010 May 2024 NextEra Energy Seabrook, LLC, License Amendment Request - One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite Transmission Network and the Onsite Class 1E Distributio ML24046A0512024-05-0707 May 2024 Issuance of Amendment No. 174 to Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (LTOP) Curves ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-078, 2023 Annual Radioactive Effluent Release Report2024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report L-2024-077, 2023 Annual Radiological Environmental Operating Report2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report IR 05000443/20245012024-04-22022 April 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000443/2024501 L-2024-058, Condition Prohibited by Technical Specifications - Transformer Bushing Failure - Offsite AC Sources2024-04-19019 April 2024 Condition Prohibited by Technical Specifications - Transformer Bushing Failure - Offsite AC Sources SBK-L-24030, 2023 Annual Environmental Operating Report2024-04-12012 April 2024 2023 Annual Environmental Operating Report L-2024-011, and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications ML24067A2622024-03-0808 March 2024 Issuance of Amendment No. 173 Revise Technical Specification 3/4.8.1 to Allow Replacement of Reserve Auxiliary Transformer (Emergency Circumstances) L-2024-038, to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0808 March 2024 to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source L-2024-037, to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0606 March 2024 to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source ML24065A2522024-03-0505 March 2024 Notice of Enforcement Discretion for Seabrook Station, Unit No. 1 (EPID: L-2024-033) L-2024-035, Supplement to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0505 March 2024 Supplement to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source L-2024-033, Request for Enforcement Discretion - Technical Specification (TS) 3/4.8.1.1 Ac. Sources Required Action Completion Time to Replace ED-X-3-B2024-03-0404 March 2024 Request for Enforcement Discretion - Technical Specification (TS) 3/4.8.1.1 Ac. Sources Required Action Completion Time to Replace ED-X-3-B L-2024-032, Emergency License Amendment Request- One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0404 March 2024 Emergency License Amendment Request- One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source IR 05000443/20230062024-02-28028 February 2024 Annual Assessment Letter for Seabrook Station (Report 05000443/2023006) L-2024-019, Relief Request 4A-01- Request for an Alternative to the Requirements of the ASME Code for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld2024-02-28028 February 2024 Relief Request 4A-01- Request for an Alternative to the Requirements of the ASME Code for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld L-2024-016, Radiological Emergency Plan (Ssrep), Revision 822024-02-13013 February 2024 Radiological Emergency Plan (Ssrep), Revision 82 IR 05000443/20230042024-02-12012 February 2024 Integrated Inspection Report 05000443/2023004 ML24009A1152024-01-29029 January 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L 2023 LLE-0043 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24022A0652024-01-22022 January 2024 Senior Reactor and Reactor Operator Initial License Examinations L-2024-003, NextEra Energy Seabrook, LLC - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2024-01-11011 January 2024 NextEra Energy Seabrook, LLC - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report ML23312A1822023-12-22022 December 2023 Issuance of Amendment No. 172 Revision to Cooling Tower Service Water Loop or Cell Requirements L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update 2024-09-25
[Table view] Category:Technical Specifications
MONTHYEARML24046A0512024-05-0707 May 2024 Issuance of Amendment No. 174 to Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (LTOP) Curves ML24067A2622024-03-0808 March 2024 Issuance of Amendment No. 173 Revise Technical Specification 3/4.8.1 to Allow Replacement of Reserve Auxiliary Transformer (Emergency Circumstances) 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 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 2024-05-07
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NEXTeraENERG-YV,January 31, 201310 CFR 50.90SBK-L-1 2266Docket No. 50-443U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555-0001Seabrook StationSupplement to License Amendment Request 10-02, "Application for Change to the TechnicalSpecifications for the Containment Enclosure Emergency Air Cleanup System"References:1. NextEra Energy Seabrook, LLC letter SBK-L-1 0074, "Application for Change to theTechnical Specifications for the Containment Enclosure Emergency Air CleanupSystem," May 14, 20102. NextEra Energy Seabrook, LLC letter SBK-L-10143, Response to Request for AdditionalInformation Regarding License Amendment Request (LAR) 10-02, "Application forChange to the Technical Specifications for the Containment Enclosure Emergency AirCleanup System," August 24, 20103. NextEra Energy Seabrook, LLC letter SBK-L-1 1184, Response to Request for AdditionalInformation Regarding License Amendment Request 10-02, Regarding the ContainmentEnclosure Emergency Air Cleanup System, September 16, 20114. NextEra Energy Seabrook, LLC letter SBK-L-12054, Response to Request for AdditionalInformation Regarding License Amendment Request 10-02, "Application for Change tothe Technical Specifications for the Containment Enclosure Emergency Air CleanupSystem," March 15, 20125. NRC letter "Seabrook Station, Unit 1 -Request for Additional Information Regarding theAddition of Action Statement to Limiting Condition for Operation 3.6.5.1, "ContainmentEnclosure Emergency Air Cleanup System" (TAC No. ME3988)," June 11, 20126. NextEra Energy Seabrook, LLC letter SBK-L-1 2124, Response to Request for AdditionalInformation Regarding License Amendment Request 10-02, Regarding the ContainmentEnclosure Emergency Air Cleanup System, July 2, 2012NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874 A 00 United States Nuclear Regulatory CommissionSBK-L-1 2266 / Page 2In Reference 1 and supplemented by References 2, 3, 4, and 6, NextEra Energy Seabrook, LLC(NextEra) submitted a request for an amendment to the Technical Specifications (TS) forSeabrook Station. The proposed amendment would relocate TS Surveillance Requirement (SR)4.6.5.1 .d.4, which verifies the ability to establish a negative pressure in the containmentenclosure building, so that it will demonstrate integrity of the containment enclosure buildingrather than operability of the containment enclosure emergency air cleanup system. Theamendment relocates SR 4.6.5.1.d.4 with modifications as new SR 4.6.5.2.b. Additionally, theamendment makes some minor wording changes, deletes a definition, and removes an expiredfootnote.The proposed change would resolve a discrepancy in required actions between TS 3.6.5.1 forthe Containment Enclosure Emergency Air Cleanup System (CEEACS), and TS 3.6.5.2,Containment Enclosure Building Integrity. Currently, TS 3.6.5.2 allows 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restorecontainment enclosure building integrity. However, the same condition (lack of containmentenclosure building integrity) would require entry into TS 3.0.3 for two inoperable trains ofCEEACS due to an inoperable ventilation area boundary. The proposed change will resolve thisdiscrepancy so that only the actions of TS 3.6.5.2 would apply to a failure to maintaincontainment enclosure building integrity.The NRC issued a similar change in February 1996 for Millstone 3 in Amendment 126. Thesafety evaluation (SE) for the amendment discusses that a conflict was identified relative toMillstone TS 3.6.6.1, Supplementary Leak Collection and Release Systems (SLCRS), duringplanned breaches of the secondary containment. TS 3.6.6.2, Secondary Containment, provides24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore secondary containment boundary operability. However, a planned breach inthe secondary containment would render both trains of SLCRS inoperable (due to the inability tosatisfy the surveillance requirement that demonstrates the ability to establish a negativepressure in the secondary containment). This condition would require a plant shutdown inaccordance with TS 3.0.3. The NRC staff's SE states that the proposed changes will resolvethis problem by decoupling TS 3.6.6.1 and 3.6.6.2; the licensee will, when breaching thesecondary containment, enter only the Action Statements for TS 3.6.6.2. In the event thatsecondary containment operability is not maintained, the Action Statement for LCO 3.6.6.2requires that secondary containment operability must be restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Further, theSE states "The staff has determined that 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is a reasonable completion time consideringthe limited leakage design of containment and the low probability of a design basis accidentoccurring during this period." Moreover, the SE states "This situation was recognized by thestaff and has been addressed in the improved standard technical specification for Westinghouseplants (NUREG-1431)."In NUREG-1431, the surveillance requirement that verifies the ability to maintain a negativepressure in the shield building is associated with TS 3.6.8, Shield Building, rather than TS3.6.13, Shield Building Air Cleanup System (SBACS), as a demonstration of shield buildingintegrity. Therefore, a failure to maintain shield building integrity does not render both trains ofthe SBACS inoperable. Furthermore, similar to the change approved for Millstone inAmendment 126, NUREG -1431 provides a 24-hour completion time to restore an inoperableshield building. The basis for this completion time included in NUREG-1431 is also the same asthat approved for Millstone 3: Twenty-four hours is a reasonable Completion Time consideringthe limited leakage design of containment and the low probability of a Design Basis Accidentoccurring during this time period.
United States Nuclear Regulatory CommissionSBK-L-1 2266 / Page 3NextEra is proposing a change to eliminate the TS discrepancy that would require a TS 3.0.3plant shutdown for a failure to maintain containment enclosure building integrity. The currentSeabrook TS provide a 24-hour completion time to restore containment enclosure buildingintegrity; however, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is not an acceptable completion time for a loss of function for theSeabrook containment enclosure building because the building access openings contain asingle door. Therefore, to avoid an unnecessary, immediate plant shutdown in the event thatcontainment enclosure building integrity is not maintained, NextEra proposes to supplement therequested amendment. The supplement provides new required actions that are based on thecause of the loss of integrity and includes a new action with a completion time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.NextEra discussed the revised proposed changes with the NRC staff in a conference call onJanuary 17, 2013.Proposed action a provides 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to restore containment enclosure building integrity whenperforming corrective or preventative maintenance on the containment enclosure boundary orfollowing discovery of an inoperable containment enclosure boundary component (penetrationseal, damper, or access door). Twelve hours is a reasonable completion time considering thelimited leakage design of containment, the low probability of a design basis accident occurringduring this time, and the time required to repair a containment enclosure building door. Further,without containment enclosure building integrity, the containment building spray (CBS) systemprovides additional defense-in-depth for accidents that credit the containment enclosurebuilding. The CBS system functions to remove iodine and reduce containment pressure, whichreduces containment leakage to the containment enclosure. As a result, the CBS systemreduces dose consequences from a release from the primary containment. Without at least oneCBS train operable, the TS require an immediate plant shutdown.Proposed action b provides a 24-hour completion time for the condition in which an operablecontainment enclosure boundary door is held open to support movement of equipment throughthe access opening, or routing hoses, cables, etc., through the access opening. This actionrequires the availability of a dedicated individual with a preplanned method to rapidly close thecontainment enclosure boundary door in the event of actuation of the CEEACS. The dedicatedindividual must be stationed at the door and have continuous communications capability with thecontrol room. Hoses and cables running through the access opening must employ a means thatallows prompt removal of the obstruction to permit closure of the door without delay. Twenty-four hours is a reasonable completion time considering the limited leakage design ofcontainment, the low probability of a DBA occurring during this time, and the availability of adedicated individual to close the containment enclosure boundary door.Attachment 1 provides a revised markup of the TS showing the proposed changes, whichreplaces and supersedes the markup of TS 3.6.5.2 provided in Reference 6, and Attachment 2contains the retyped TS page. Attachment 3 provides revised TS Bases that replace andsupersede the proposed Bases for TS 3.6.5.2 provided in Reference 6. The Bases are providedfor information and will be implemented in accordance with TS 6.7.6.j, TS Bases ControlProgram, upon implementation of the license amendment.The modification to the proposed change does not alter the conclusion in Reference 1 that theproposed change does not involve a significant hazard consideration pursuant to 10 CFR 50.92.
United States Nuclear Regulatory CommissionSBK-L-1 2266 / Page 4A copy of this letter has been forwarded to the New Hampshire State Liaison Officer pursuant to10 CFR 50.91(b).Should you have any questions regarding this letter, please contact Mr. Michael O'Keefe,Licensing Manager, at (603) 773-7745.Sincerely,NextEra Energy Seabrook, LLCKevin T. WalshSite Vice PresidentEnclosurecc: NRC Region I AdministratorJ. G. Lamb, NRC Project Manager, Project Directorate 1-2NRC Senior Resident InspectorPerry E. Plummer, Acting Director, Homeland Security and Emergency ManagementNew Hampshire Department of SafetyDivision of Homeland Security and Emergency ManagementBureau of Emergency Management33 Hazen DriveConcord, NH 03305John Giarrusso, Jr., Nuclear Preparedness ManagerThe Commonwealth of MassachusettsEmergency Management Agency400 Worcester RoadFramingham, MA 01702-5399 NExTeraoENERGY dAFFIDAVITSEABROOK STATION UNIT 1Facility Operating License NPF-86Docket No.50-443Supplement to License Amendment Request 10-02, "Application for Change to theTechnical Specifications for the Containment Enclosure Emergency Air Cleanup System"I, Kevin T. Walsh, Site Vice President of NextEra Energy Seabrook, LLC hereby affirm thatthe information and statements contained within this supplement regarding LicenseAmendment Request 10-02 are based on facts and circumstances which are true andaccurate to the best of my knowledge and belief.Sworn and Subscribedbefore me this\ day of u &. ,2013N~ayPublic)Kevin T. WalshSite Vice President
Attachment
1Markup of TS 3.6.5.2 CONTAINMENT SYSTEMSCONTAINMENT ENCLOSURE BUILDINGCONTAINMENT ENCLOSURE BUILDING INTEGRITYLIMITING CONDITION FOR OPERATION3,6.5.2 BULLDNG I, TE-$RI shall be maintained.APPLICABILITY: MODES 1, 2, 3, and 4.ACTION: '- 'a",,( itho ONTA ~T ENCL S RE BQILDI~G r tore CO~ANM NT)LOS RE DING VJ lFT{Ywith~iq hour or b least ~ S DYwithin =then nt 6hou s and ih.COLD SH LfDOWN with the'follio-w 3 osSURVEILLANCE REQUIREMENTS4.6.5.2 ENT E WO,2'UR EeUI L G Na .shall be demonstratedol-ieasn5 per "lay~sby veifying What the doortn each aclcefssop~eniing is c~losed the accesenin cis beýing used for normal transit entry a~nd exi .Il,?-/4 aye,?1"71SEABROOK -UNIT 13/4 6-24 INSERT NOTE---------------------------------IL jI'--------------------------------------------------Entry into ACTION is not required when the access opening is being usedfor normal transit entry or exit.............................................................................................................INSERT ACTIONSa. Without containment enclosure building integrity for reasons other than Action b, restorecontainment enclosure building integrity within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Otherwise be in at least HOTSTANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30hours.b. Without containment enclosure building integrity when equipment ingress and egressrequires the access door to be maintained open, verify a dedicated individual, who is incontinuous communication with the control room, is available to rapidly close the door;and restore containment enclosure building integrity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Otherwise be in atleast 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 /> and in COLD SHUTDOWN within thefollowing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Attachment
2Retyped Page for TS 3.6.5.2 CONTAINMENT SYSTEMSCONTAINMENT ENCLOSURE BUILDINGCONTAINMENT ENCLOSURE BUILDING INTEGRITYLIMITING CONDITION FOR OPERATION3.6.5.2 Containment enclosure building integrity shall be maintained.APPLICABILITY: MODES 1, 2, 3, and 4.------------------------NOTE ---------------------------Entry into ACTION is not required when the access opening is being usedfor normal transit entry or exit.ACTION:a. Without containment enclosure building integrity for reasons other than Action b, restorecontainment enclosure building integrity within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Otherwise be in at least HOTSTANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30hours.b. Without containment enclosure building integrity when equipment ingress and egressrequires the access door to be maintained open, verify a dedicated individual, who is incontinuous communication with the control room, is available to rapidly close the door;and restore containment enclosure building integrity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Otherwise be in atleast 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 /> and in COLD SHUTDOWN within thefollowing 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />sSURVEILLANCE REQUIREMENTS4.6.5.2 Containment enclosure building integrity shall be demonstrated:a. At least once per 31 days by verifying that the door in each access opening isclosed except when the access opening is being used for normal transit entryand exit, andb. At least once per 36 months on a STAGGERED TEST BASIS by verifying thecontainment enclosure building can be maintained at a negative pressuregreater than or equal to 0.25 inch water gauge by one train of the containmentenclosure emergency air cleanup system within 4 minutes after a start signal.SEABROOK -UNIT 13/4 6-23Amendment No.
Attachment
3Bases for TS 3.6.5.2 3/4.6.5.2 CONTAINMENT ENCLOSURE BUILDING INTEGRITYBACKGROUNDThe containment enclosure building is a reinforced concrete right cylindrical structure with ahemispherical dome that is located outside and surrounds the containment building. Thisstructure provides leak protection for the containment and protects it from certain loads (normalloads, loads due to severe and extreme environmental conditions, and abnormal loads). Thespace between the containment and the enclosure building is maintained at a slight negativepressure during accident conditions. All joints and penetrations are sealed to ensure airtightness.Without containment enclosure building integrity, the containment building spray (CBS) systemprovides additional defense-in-depth for accidents that credit the containment enclosurebuilding. The CBS system functions to remove iodine and reduce containment pressure, whichreduces containment leakage to the containment enclosure. As a result, the CBS systemreduces dose consequences from a release from the primary containment. When Action a or bis entered, the plant can continue to operate at power if at least one CBS train is operable inaccordance with TS 3.6.2.1.APPLICABLE SAFETY ANALYSESThe function of the containment enclosure building is to collect any fission products which couldleak from the primary containment structure into the containment enclosure and contiguousareas following a LOCA. The containment enclosure provides a barrier between thecontainment and the environment to control all leakage out from the containment boundary.Containment enclosure building integrity ensures that the release of radioactive materials fromthe primary containment atmosphere will be restricted to those leakage paths and associatedleak rates assumed in the safety analyses. This restriction, in conjunction with operation of thecontainment enclosure emergency air cleanup system (CEEACS), will limit radiation dose towithin the dose guideline values of 10 CFR 50.67 during accident conditions.The containment enclosure building satisfies Criterion 3 of 10 CFR 50.36(c)(2)(ii).LCOContainment enclosure building integrity must be maintained to limit the release of radioactivematerials from the primary containment atmosphere to those leakage paths and associated leakrates assumed in the safety analyses. Containment enclosure building integrity exists when (1)each door in each access opening is closed except when the access opening is being used fornormal transit entry and exit, (2) the sealing mechanism associated with each containmentenclosure building penetration (e.g., welds, bellows, or 0-rings) is OPERABLE, and (3) thecontainment enclosure building functions as designed to maintain the required negativepressure.APPLICABILITYMaintaining containment enclosure building integrity prevents leakage of radioactive materialfrom the enclosure building. Radioactive material may enter the containment enclosure buildingfrom the containment following a DBA. Therefore, containment enclosure integrity is required in1 MODES 1, 2, 3, and 4 when a DBA could release radioactive material to the containmentatmosphere. In MODES 5 and 6, the probability and consequences of these events are low dueto the Reactor Coolant System temperature and pressure limitations in these MODES.Therefore, containment enclosure building integrity is not required in MODE 5 or 6.ACTIONSA Note states that entry into the Actions is not required when an access opening (containmentenclosure boundary door) is being used for normal transit entry and exit. This provision providesan exception to TS 3.0.1 when containment enclosure integrity is not maintained while anaccess door is open for normal transit. This note is consistent with SR 4.6.5.2.a, which requireseach containment enclosure boundary door to be closed except during normal transit entry andexit.Action a.Action a addresses a loss of containment enclosure building integrity for reasons other thanprovided in Action b. For example, this action is applicable when performing preventative orcorrective maintenance on the containment enclosure building boundary, including containmentenclosure building penetration seals, dampers and access doors, that results in a failure tomaintain containment enclosure building integrity. The containment enclosure building accessopenings contain a single door, so opening a door causes a loss of containment enclosureintegrity.Containment building enclosure integrity must be restored within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Twelve hours is areasonable completion time considering the limited leakage design of containment, the lowprobability of a DBA occurring during this time, and the time required to repair a containmentenclosure building door.Action b.Action b addresses the condition in which an OPERABLE containment enclosure boundary dooris held open to support movement of equipment through the access opening, or routing hoses,cables, etc., through the access opening. Thus, this action applies when containment enclosurebuilding integrity is not maintained due to an open access door for equipment ingress andegress because the doorway must be maintained open, i.e., obstructed, for equipment, cables,hoses, etc., such that it cannot be immediately closed. Additionally, pressure boundary sealsmust also be intact to maintain the integrity of the containment enclosure. Action b does notapply to normal transit entry and exit.Action b requires the availability of a dedicated individual with a preplanned method to rapidlyclose the containment enclosure boundary door in the event of actuation of the CEEACS. Thededicated individual must be stationed at the door and have continuous communicationscapability with the control room. Hoses and cables running through the access opening mustemploy a means that allows prompt removal of the obstruction to permit closure of the doorwithout delay.Containment building enclosure integrity must be restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Twenty-four hours isa reasonable completion time considering the limited leakage design of containment, the lowprobability of a DBA occurring during this time, and the availability of a dedicated individual toclose the containment enclosure boundary door.2 SURVEILLANCE REQUIREMENTSSR 4.6.5.2.aThe containment enclosure boundary doors are normally maintained closed except when theaccess opening is being used for entry and exit. Verifying containment enclosure buildingintegrity involves confirming that the doors are closed except during normal transit entry and exit.Normal transit includes opening doors as necessary to permit the movement of people andequipment through the doorway. This may also include opening doors to test actuation of dooralarms. Propping open a door and obstructing the doorway with equipment, cables, hoses, etc.,such that it cannot be immediately closed is not normal transit entry and exit. Additionally,pressure boundary seals must also be intact to maintain the integrity of the containmentenclosure.SR 4.6.5.2.bThe CEEACS is used to establish a negative pressure in the containment enclosure building.SR 4.6.5.2 verifies containment enclosure building integrity by drawing down the containmentenclosure building to a negative pressure greater than or equal to 0.25 inch Water Gauge usingone train of CEEACS within four minutes after a start signal to ensure that the building can meetits design negative pressure in less than eight minutes following the initiation of a LOCA.Inoperability of the containment enclosure building does not by itself render the CEEACSinoperable. Therefore, the Action of TS 3.6.5.1 (CEEACS) is not required to be entered solelydue to a failure to maintain containment enclosure building integrity.Since this SR is a containment enclosure building boundary integrity test, it does not need to beperformed at each surveillance interval with each CEEACS train. The CEEACS train used forthis SR is scheduled on a STAGGERED test basis to ensure that either train will perform thetest. The primary purpose of this SR is to ensure containment enclosure building integrity. Thesecondary purpose of this SR is to ensure that the CEEACS train used for the test functions asdesigned. Inoperability of the CEEACS train does not necessarily constitute a failure of this SRrelative to containment enclosure building integrity.3