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MONTHYEARML0408603072004-03-17017 March 2004 License Amendment Request 04-03, Application for Stretch Power Uprate Project stage: Request ML0408500742004-03-17017 March 2004 Transmittal of Proprietary Information to Support License Amendment Request 04-03, Application for Stretch Power Uprate Project stage: Request ML0410501752004-04-0101 April 2004 Background Information to Support License Amendment Request 04-03, Application for Stretch Power Uprate Project stage: Request ML0411906062004-04-28028 April 2004 Draft Request for Additional Information Project stage: Draft RAI ML0415603392004-05-26026 May 2004 Response to Request for Additional Information Regarding License Amendment Request 04-03, Application for Stretch Power Uprate Project stage: Response to RAI ML0415901572004-06-10010 June 2004 FPL Energy Seabrook, LLC - Stretch Power Uprate Acceptance Review for Seabrook Station, Unit No. 1 Project stage: Acceptance Review ML0421900852004-08-18018 August 2004 Request for Additional Information for Proposed Amendment Request Regarding the Application for Stretch Power Uprate Project stage: RAI ML0423607522004-08-24024 August 2004 Draft Request for Additional Information Project stage: Draft RAI ML0424600712004-09-0202 September 2004 Draft Request for Additional Information Project stage: Draft RAI SBK-L-04049, Response to Request for Additional Information Regarding License Amendment Request 03.02.2004-09-13013 September 2004 Response to Request for Additional Information Regarding License Amendment Request 03.02. Project stage: Response to RAI SBK-L-04052, Re-submittal of Proprietary Information to Support License Amendment Request 04-03, Application for Stretch Power Uprate2004-09-13013 September 2004 Re-submittal of Proprietary Information to Support License Amendment Request 04-03, Application for Stretch Power Uprate Project stage: Request SBK-L-04044, Changes to License Amendment Request 04-03, Application for Stretch Power Uprate2004-09-13013 September 2004 Changes to License Amendment Request 04-03, Application for Stretch Power Uprate Project stage: Request ML0424003652004-09-15015 September 2004 Memo, Advisory Committee on Reactor Safety Review of Stretch Power Uprate Amendment Project stage: Approval ML0428902812004-10-12012 October 2004 Response to Request for Additional Information Regarding License Amendment Request 04-03, Application for Stretch Power Uprate Project stage: Response to RAI ML0818505222004-10-13013 October 2004 Advisory Committee on Reactor Safeguards Review of Stretch Power Uprate Amendment Project stage: Approval ML0409804772004-10-14014 October 2004 Request for Withholding Information from Public Disclosure, Stretch Power Uprate NSSS Licensing Report Supplemental Information, WCAP-16223-NP Project stage: Withholding Request Acceptance SBK-L-04095, Revision to Response to Request for Additional Information Regarding License Amendment Request 04-03. Application for Stretch Power Uprate2004-10-28028 October 2004 Revision to Response to Request for Additional Information Regarding License Amendment Request 04-03. Application for Stretch Power Uprate Project stage: Response to RAI ML0430803222004-11-19019 November 2004 Withholding from Public Disclosure, Westinghouse Responses to NRC Requests for Additional Information (Rais) for Seabrook Station Stretch Power Uprate (Proprietary) Project stage: RAI SBK-L-04116, Supplemental Response to Request for Additional Information (RAI Nos. 2 and 3) Regarding License Amendment Request 04-03. Application for Stretch Power Uprate2004-12-0303 December 2004 Supplemental Response to Request for Additional Information (RAI Nos. 2 and 3) Regarding License Amendment Request 04-03. Application for Stretch Power Uprate Project stage: Supplement ML0429300082004-12-0808 December 2004 Environmental Assessment and Finding of No Significant Impact - Power Uprate Modification Project stage: Other ML0435000312004-12-15015 December 2004 Facsimile Transmission, Draft Request for Additional Information Project stage: Draft RAI SBK-L-04135, Supplemental Response to Request for Additional Information Regarding License Amendment Request 04-03. Application for Stretch Power Uprate2004-12-28028 December 2004 Supplemental Response to Request for Additional Information Regarding License Amendment Request 04-03. Application for Stretch Power Uprate Project stage: Supplement ML0503901482005-02-0808 February 2005 Publication in Federal Register of Individual Notice Transmitting Environmental Assessment Project stage: Other SBK-L-05032, Supplemental Response to Request for Additional Information Regarding License Amendment Request 04-03, Application for Stretch Power Uprate2005-02-0909 February 2005 Supplemental Response to Request for Additional Information Regarding License Amendment Request 04-03, Application for Stretch Power Uprate Project stage: Supplement SBK-L-05054, Supplemental Response to Request for Additional Information Regarding License Amendment Request 04-03, Application for Stretch Power Uprate2005-02-25025 February 2005 Supplemental Response to Request for Additional Information Regarding License Amendment Request 04-03, Application for Stretch Power Uprate Project stage: Supplement ML0501404532005-02-28028 February 2005 License Amendment, Increase the Licensed Rated Power by 5.2 Percent from 3411 Megawatts Thermal to 3587 Megawatts Thermal Project stage: Acceptance Review 2004-04-28
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Category:Environmental Assessment
MONTHYEARML21062A1472021-04-21021 April 2021 Final Environmental Assessment and Finding of No Significant Impact of 2012 and 2015 Decommissioning Funding Plans for Seabrook Station Unit 1 Independent Spent Fuel Storage Installation SBK-L-10039, Request for Exemption from Specific 10 CFR 73 Requirements, Physical Protection of Plants and Materials.2010-02-25025 February 2010 Request for Exemption from Specific 10 CFR 73 Requirements, Physical Protection of Plants and Materials. ML0529204492005-12-0606 December 2005 Environmental Assessment ML0429300082004-12-0808 December 2004 Environmental Assessment and Finding of No Significant Impact - Power Uprate Modification ML0316405792003-07-21021 July 2003 Environmental Assessment Exemption Request ML0205105942002-03-27027 March 2002 Environmental Assessment Related to Administrative Technical Specification Amendment (Tac No. MB2852) 2021-04-21
[Table view] Category:Federal Register Notice
MONTHYEARML20177A6452020-07-15015 July 2020 FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for June 2020 ML20119A5242020-05-0707 May 2020 FRN: Notice of Issuance of Multiple Exemptions Regarding 10 CFR Part 26 (COVID-19) ML19282C6142019-10-22022 October 2019 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing ML19282B8322019-10-22022 October 2019 Cover Letter with Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opp. for a Hearing ML19238A3692019-09-0303 September 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 09/10/2019 ML19085A2172019-03-29029 March 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 04/09/2019 NRC-2019-0075, Federal Register Notice - License Amendment; Issuance (CAC No. MF8260; EPID L-2016-LLA-0007)2019-03-12012 March 2019 Federal Register Notice - License Amendment; Issuance (CAC No. MF8260; EPID L-2016-LLA-0007) ML18204A2422019-03-12012 March 2019 Federal Register Notice - License Amendment; Issuance (CAC No. MF8260; EPID L-2016-LLA-0007) ML18345A2322019-03-12012 March 2019 Federal Register Notice - Issuance of Renewed Facility Operating License No. NPF-86 for Seabrook Station, Unit 1 ML19015A1832019-03-11011 March 2019 Notice of Issuance of License Amendment to Facility Operating License No. NPF-86 (CAC No. MF8260; EPID L-2016-LLA-0007) ML17031A3652017-02-15015 February 2017 Order Prohibiting Involvement in NRC-Licensed Activities and Notice of Violation (NRC Office of Investigations Report No. 1-2015-029) (IA-16-075) ML17003A2422017-01-24024 January 2017 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Consideration and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Publication Date: February 7, ML16271A0922016-09-28028 September 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: October 11, 2016 ML16131A7952016-05-13013 May 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 24, 2016 NRC-2016-0100, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 24, 20162016-05-13013 May 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 24, 2016 ML15096A1432015-07-28028 July 2015 Exemption from Specific Requirements of 10 CFR Part 50, Appendix G, and 10 CFR 50.60 NRC-2015-0184, Exemption2015-07-28028 July 2015 Exemption ML15092A5192015-07-28028 July 2015 Exemption ML15204A2792015-07-27027 July 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 4, 2015 ML15148A3762015-06-0101 June 2015 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Published June 9, 2015 ML15120A2272015-05-0101 May 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 12, 2015 ML13018A2392015-04-0808 April 2015 G20110171 - Letter to Petitioner Saporito on Proposed Director'S Decision Regarding 2.206 Petition Dated: March 12, 2011 ML14233A2082014-08-22022 August 2014 Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 2, 2014 NRC-2014-0193, Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 2, 20142014-08-22022 August 2014 Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 2, 2014 NRC-2014-0008, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures fo2014-01-22022 January 2014 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Add ML14007A2192014-01-22022 January 2014 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Add ML13225A5572013-08-12012 August 2013 Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit ML13228A3992013-08-12012 August 2013 Letter to Holders of Independent Spent Fuel Storage Installation (ISFSI) Licenses Re Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit - Rin 3150-AI64 (NRC-2009-0163) EA-02-109 ML12152A3162012-06-12012 June 2012 Biweekly Sholly Report - Federal Register Notice - Fr Publication June 12, 2012 ML12158A2612012-06-0606 June 2012 Federal Register Notice Regarding the ACRS Plant License Renewal (Seabrook) Subcommittee Meeting, July 10, 2012 ML12109A4272012-05-31031 May 2012 Notice of Intent to Prepare a Supplement to Draft Supplement 46 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Seabrook Station ML12109A4022012-05-31031 May 2012 Notice of Intent to Prepare a Supplement to Draft Supplement 46 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Seabrook Station NRC-2012-0067, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status2012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML12056A0442012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML11349A0052011-12-15015 December 2011 Biweekly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations: Fr Publication Date December 27, 2011 NRC-2011-0290, Biweekly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations: Fr Publication Date December 27, 20112011-12-15015 December 2011 Biweekly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations: Fr Publication Date December 27, 2011 ML11237A0072011-08-25025 August 2011 FRN: General Notice. Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 9/6/11 NRC-2011-0205, FRN: General Notice. Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 9/6/112011-08-25025 August 2011 FRN: General Notice. Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 9/6/11 ML11131A0052011-08-0101 August 2011 NRC Nextera Energy Seabrook, LLC Notice of Availability of Draft Supplement 46 to the GEIS for License Renewal of Nuclear Plants and Public Meetings for the License Renewal of Seabrook Station,Unit 1 Docket No. 50-443 (NRC-2010-0206) ML1111802212011-05-0202 May 2011 Withdrawal of License Amendment Request 10-06 ML1103502482011-03-0101 March 2011 License Amendment, Issuance of Amendment, the Proposed Amendment Would Modify Technical Specification 6.7.6.k, Steam Generator, and Technical Specification 6.8.1.7, Steam Generator Tube Inspection Report. ML1103502522011-02-23023 February 2011 Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, Opportunity for a Hearing, and Order Imposing Procedures for Document Access.. NRC-2011-0044, Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, Opportunity for a Hearing, and Order Imposing Procedures for Document Access..2011-02-23023 February 2011 Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, Opportunity for a Hearing, and Order Imposing Procedures for Document Access.. ML1019000132010-07-20020 July 2010 08/19/2010-Forthcoming Meeting to Discuss the License Renewal Process and Environmental Scoping for Seabrook Station License Renewal Application Review ML1016904492010-07-13013 July 2010 Notice of Acceptance for Docketing of the Application and Notice of Opportunity for Hearing Regarding Renewal of Facility Operating License No. NPF-086 for an Additional 20-year Period ML1016804272010-07-13013 July 2010 Notice of Intent to Prepare an Environmental Impact Statement and Conduct the Scoping Process for License Renewal for Seabrook Station - FRN ML1013300492010-06-10010 June 2010 Notice of Receipt and Availability for Seabrook Station License Renewal Application (FRN) ML0911306172009-04-24024 April 2009 Biweekly Notice, Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations ML0905800142009-02-26026 February 2009 Sholly Report for Fr Publication Date March 10th 2009 ML0807100432008-03-12012 March 2008 Individual Federal Register Notice-Seabrook Station, Unit No. 1-Individual Notice of Consideration of Issuance of Amendment Concerning the Revision of Nuclear Instrumentation Surveillance Requirement 2020-07-15
[Table view] Category:Finding of No Significant Impact
MONTHYEARML0429300082004-12-0808 December 2004 Environmental Assessment and Finding of No Significant Impact - Power Uprate Modification ML0316405792003-07-21021 July 2003 Environmental Assessment Exemption Request 2004-12-08
[Table view] Category:Letter
MONTHYEARML24009A1152024-01-29029 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 L-2023-180, Submittal of Changes to the Technical Specification Bases2023-12-13013 December 2023 Submittal of Changes to the Technical Specification Bases L-2023-177, Supplement to Seabrook Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Seabrook Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-160, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Final Rule ML23318A0772023-11-14014 November 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000443/2024011 IR 05000443/20234032023-11-0707 November 2023 Security Baseline Inspection Report 05000443/2023403 and Independent Spent Fuel Storage Installation 07200063/2023401 IR 05000443/20230032023-11-0606 November 2023 Integrated Inspection Report 05000443/2023003 IR 05000443/20230102023-10-19019 October 2023 Triennial Fire Protection Inspection Report 05000443/2023010 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23275A0522023-10-0202 October 2023 Requalification Program Inspection IR 05000443/20234012023-09-0808 September 2023 Cybersecurity Inspection Report 05000443/2023401 (Cover Letter Only) IR 05000443/20234202023-09-0505 September 2023 Security Baseline Inspection Report 05000443/2023420 IR 05000443/20230052023-08-31031 August 2023 Updated Inspection Plan for Seabrook Station (Report 05000443/2023005) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update IR 05000443/20233022023-08-16016 August 2023 Operator Licensing Retake Examination Report 05000443/2023302 IR 05000443/20230022023-08-0808 August 2023 Integrated Inspection Report 05000443/2023002 L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment L-2023-104, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-103, Inservice Inspection Examination Report2023-08-0303 August 2023 Inservice Inspection Examination Report ML23192A0782023-07-11011 July 2023 Operator Licensing Retake Examination Approval L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) SBK-L-23053, Radiological Emergency Plan (Ssrep), Revision 802023-06-22022 June 2023 Radiological Emergency Plan (Ssrep), Revision 80 ML23157A0722023-06-0606 June 2023 Notification of Conduct of a Fire Protection Team Inspection L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal IR 05000443/20233012023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000443/2023301 L-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 IR 05000443/20230012023-05-11011 May 2023 Integrated Inspection Report 05000443/2023001 ML23129A0312023-05-0909 May 2023 Reactor Operator Retake License Examination ML23117A3652023-05-0404 May 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Remove Period of Applicability from PTL and Low Temperature Over Pressure Protection Curves SBK-L-23044, 2022 Annual Radiological Environmental Operating Report2023-04-28028 April 2023 2022 Annual Radiological Environmental Operating Report SBK-L-23031, 2022 Annual Radioactive Effluent Release Report2023-04-28028 April 2023 2022 Annual Radioactive Effluent Release Report SBK-L-23033, 2022 Annual Environmental Operating Report2023-04-11011 April 2023 2022 Annual Environmental Operating Report L-2023-053, Core Operating Limits Report for Cycle 232023-04-0505 April 2023 Core Operating Limits Report for Cycle 23 ML23088A1522023-03-29029 March 2023 Summary of Meeting Between Nrc/Region I and C-10 - Questions Regarding Seabrook 4Q2022 Inspection Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications ML23073A1562023-03-23023 March 2023 Relief Request 4RA-22-01, Relief from the Requirements of the ASME Code 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-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-023, Revised Steam Generator Tube Inspection Report2023-03-0303 March 2023 Revised Steam Generator Tube Inspection Report ML23020A1002023-03-0303 March 2023 OEDO-22-00419 - 2.206 Petition for Seabrook Station Structure Concrete Concerns (EPID L-2022-CRS-0000)- Closure Letter 2024-01-29
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Text
December 8, 2004 Mr. Mark E. Warner, Site Vice President c/o James M. Peschel Seabrook Station P.O. Box 300 Seabrook, NH 03874
SUBJECT:
SEABROOK STATION, UNIT NO. 1 - ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT - POWER UPRATE MODIFICATION (TAC NO. MC2364)
Dear Mr. Warner:
Enclosed is a copy of the Environmental Assessment and Finding of No Significant Impact related to your application for an amendment to permit uprated power operations at Seabrook Station, Unit No. 1 (Seabrook) dated March 17, 2004, as supplemented by a second letter dated March 17, 2004, and letters dated April 1, May 26, September 13 (two letters), and October 12, 2004. The proposed amendment would increase the licensed reactor power from 3411 megawatts thermal (MWt) to 3587 MWt at Seabrook, an approximate 5.2 percent increase.
The Environmental Assessment is being forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA/
Victor Nerses, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-443
Enclosure:
As stated cc w/encl: See next page
ML042930008 OFFICE PDI-2/PM PDI-2/LA PDIII-1/PM RLEP/SC(A) OGC PDI-2/SC NAME VNerses CRaynor JStang AKugler HMcGurren DRoberts DATE 12/03/04 11/18/04 10/28/04 11/15/04 11/24/04 12/07/04 Seabrook Station, Unit No. 1 cc:
Mr. J. A. Stall Mr. Stephen McGrail, Director Senior Vice President, Nuclear and ATTN: James Muckerheide Chief Nuclear Officer Massachusetts Emergency Management Agency Florida Power & Light Company 400 Worcester Road P.O. Box 14000 Framingham, MA 01702-5399 Juno Beach, FL 33408-0420 Philip T. McLaughlin, Attorney General Mr. Peter Brann Steven M. Houran, Deputy Attorney Assistant Attorney General General State House, Station #6 33 Capitol Street Augusta, ME 04333 Concord, NH 03301 Resident Inspector Mr. Bruce Cheney, Director U.S. Nuclear Regulatory Commission New Hampshire Office of Emergency Seabrook Nuclear Power Station Management P.O. Box 1149 State Office Park South Seabrook, NH 03874 107 Pleasant Street Concord, NH 03301 Town of Exeter 10 Front Street Mr. Gene F. St. Pierre Exeter, NH 03823 Station Director Seabrook Station Regional Administrator, Region I FPL Energy Seabrook, LLC U.S. Nuclear Regulatory Commission P.O. Box 300 475 Allendale Road Seabrook, NH 03874 King of Prussia, PA 19406 Mr. M. S. Ross, Managing Attorney Office of the Attorney General Florida Power & Light Company One Ashburton Place, 20th Floor P.O. Box 14000 Boston, MA 02108 Juno Beach, FL 33408-0420 Board of Selectmen Mr. Rajiv S. Kundalkar Town of Amesbury Vice President - Nuclear Engineering Town Hall Florida Power & Light Company Amesbury, MA 01913 P.O. Box 14000 Juno Beach, FL 33408-0420 Ms. Deborah Bell Federal Emergency Management Agency James M. Peschel Region I Regulatory Programs Manager J.W. McCormack P.O. & Seabrook Station Courthouse Building, Room 401 FPL Energy Seabrook, LLC Boston, MA 02109 PO Box 300 Seabrook, NH 03874 Mr. Tom Crimmins Polestar Applied Technology One First Street, Suite 4 Los Altos, CA 94019
Seabrook Station, Unit No. 1 cc:
David Moore Vice President, Nuclear Operations Support Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Marjan Mashhadi Senior Attorney Florida Power & Light Company 801 Pennsylvania Ave., NW Suite 220 Washington, DC 20004
7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION FPL ENERGY SEABROOK, LLC DOCKET NO. 50-443 SEABROOK STATION, UNIT NO. 1 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Title 10 of the Code of Federal Regulations (10 CFR) Section 50.90 for Facility Operating License No. NPF-86, issued to FPL Energy Seabrook, LLC (FPLE Seabrook or the licensee), for operation of the Seabrook Station, Unit No. 1 (Seabrook), located in Seabrook Township, Rockingham County, New Hampshire. Therefore, as required by 10 CFR 51.21, the NRC is issuing this environmental assessment and finding of no significant impact.
ENVIRONMENTAL ASSESSMENT Identification of the Proposed Action:
The proposed action would allow FPLE Seabrook to increase the maximum reactor core power level from 3411 megawatts thermal (MWt) to 3587 MWt, which is an increase of approximately 5.2 percent of the rated core thermal power for Seabrook.
The proposed action is in accordance with the licensees application dated March 17, 2004, as supplemented by a second letter dated March 17, 2004, and letters dated April 1, May 26, September 13 (two letters), and October 12, 2004.
The Need for the Proposed Action:
The proposed action permits an increase in the licensed core thermal power from 3411 MWt to 3587 MWt for Seabrook and provides the flexibility to increase the potential electrical output of Seabrook.
Environmental Impacts of the Proposed Action:
This assessment summarizes the non-radiological and radiological impacts on the environment that may result from the proposed action. The NRC staff based its conclusions on an analyzed core power level of 3659 MWt (3678 MWt Nuclear Steam Supply System (NSSS) power level). A power level of 3659 MWt is used based on the guaranteed core thermal output of 3587 MWt plus a 2-percent uncertainty allowance for calorimetric measurements.
Radiological Environmental Assessment:
Radwaste Systems:
Seabrook uses waste treatment systems designed to maintain normal operation offsite releases and doses within the requirements of 10 CFR Part 20 and 10 CFR Part 50, Appendix I.
Regulatory guidance relative to the methodology used to determine if the radwaste effluent releases from a pressurized-water reactor meet the requirements of 10 CFR Part 20 and 10 CFR Part 50, Appendix I is provided in NUREG-0017, Revision 1, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWR-GALE Code)." The proposed power uprate will not change existing radioactive waste system design, plant operating procedures, or waste inputs as defined by NUREG-0017. As a result, the impact of the proposed power uprate on radwaste releases and Appendix I doses can be estimated using the methodology and equations found in NUREG-0017, Revision 1.
The reactor coolant contains activated corrosion products, which are the result of metallic materials entering the water and being activated in the reactor region. Under power
uprate conditions, the feedwater flow increases with power and the activation rate in the reactor region increases with power. Additionally, non-condensible radioactive gas from the main condenser, along with air in-leakage, normally contains activation gases (principally N-16, O-19 and N-13) and fission product radioactive noble gases. This is the major source of radioactive gas. The proposed power uprate will increase the activity level of radioactive isotopes in the primary and secondary coolant. Due to leakage or process operations, fractions of these fluids are transported to the liquid and gaseous waste systems where they are processed prior to discharge. As the activity levels in the primary and secondary coolant are increased, the activity level of inputs into the waste systems are proportionately increased.
The methodology used for the processing of radioactive waste at Seabrook will not be impacted by operation at the proposed uprated power level, and the slight increase in activity discharged would continue to meet the requirements of 10 CFR Part 20, 10 CFR Part 50, Appendix I, and the annual doses projected in the Seabrook Final Environmental Statement (FES), NUREG-0895, dated December 1982. The NRC staff concludes that the proposed power uprate will not affect the ability to process liquid or gaseous radioactive effluents and the environmental impacts of the proposed power uprate are bounded by the impacts previously evaluated in the FES.
Occupational Dose:
Occupational exposure from in-plant radiation primarily occurs during routine maintenance, special maintenance, and refueling operations. An increase in power at Seabrook will increase the activity inventory of fission products in the core by approximately the percentage of the power uprate. As a result, the radioactivity levels in the primary coolant, secondary coolant, and other radioactive process systems and components will also be impacted. Based on an uprate from the current licensed core power of 3411 MWt to the analyzed core power level of 3659 MWt (3678 MWt NSSS power level), normal operation
radiation levels in areas near the reactor vessel are expected to increase but the annual average collective occupational dose after the power uprate is implemented would still be well below the value expected when the FES was published and as set in 10 CFR Part 20. In addition, plant programs and administrative controls such as shielding, plant chemistry, and the radiation protection program will help compensate for the potential increase in occupational dose. The proposed actions does not involve significant increases in the offsite doses to the public from noble gases, airborne particulates, iodine, tritium, or liquid effluents.
The NRC staff concludes that doses offsite will continue to be within the limits of 10 CFR Part 20, and the slight potential increase in occupational exposure are bounded by the impacts previously evaluated in the FES.
Postulated Accident Doses:
The licensee's uprate analysis program included a reanalysis or evaluation of all aspects of large-break loss-of-coolant accident (LOCA), small-break LOCA, non-LOCA accidents, and NSSS and balance-of-plant (BOP) structures, systems, and components. Major NSSS components (e.g., reactor pressure vessel, pressurizer, reactor coolant pumps, and steam generators); BOP components (e.g., turbine, generator, and condensate and feedwater pumps); and major systems and sub-systems (e.g., safety injection, auxiliary feedwater, residual heat removal, electrical distribution, emergency diesel generators, containment cooling, and the ultimate heat sink) have been assessed with respect to the bounding conditions expected for operation at the uprated power level. Control systems (e.g., rod control, pressurizer pressure and level, turbine overspeed, steam generator level, and steam dump) have been evaluated for operation at uprated power conditions. The results of all of the above analyses and evaluations have yielded acceptable results and demonstrate that all design basis acceptance criteria will continue to be met during uprated power operations.
For post-accident conditions, the existing post-accident dose rate maps are adequate for power uprate conditions. The resulting radiation levels were determined to be within current regulatory limits, and there would be no effect on the plant equipment, access to vital areas, or habitability of the control room. The licensee has determined that access to areas requiring post-accident occupancy will not be significantly affected by the power uprate. The calculated whole body and thyroid doses at the exclusion area boundary that might result from a postulated design-basis LOCA at uprated power conditions were determined to remain below established regulatory limits. Therefore, the NRC staff concludes that, for the proposed action, potential increased doses from postulated accidents are not significant.
Non-Radiological Environmental Assessment:
In support of the proposed action, the licensee reviewed the non-radiological environmental impacts of the power uprate based on information submitted in the Seabrook Environmental Report - Operating License Stage (ER-OL), dated June 29, 1981, the Seabrook FES, and the requirements of the Environmental Protection Plan. Based on this review, the licensee concluded that the proposed power uprate has no significant effect on the non-radiological elements of concern and the plant will be operated within the bounds of impacts previously evaluated in the FES. In addition, the licensee states that existing Federal, State, and local regulatory permits presently in effect accommodate the power uprate without modification.
Water Use Impacts:
The Atlantic Ocean serves as the normal supply of cooling water and as the ultimate heat sink for Seabrook. The cooling water is withdrawn from the Atlantic Ocean via a 17,000-foot long intake tunnel in the underlying bedrock, and is returned to the ocean through a similar discharge tunnel, approximately 16,500 feet long. The Circulating Water System (CWS) delivers cooling water from the Atlantic Ocean to the main condenser to remove the heat
rejected by the turbine cycle and auxiliary systems and conveys the heated discharge water back to the Atlantic Ocean. CWS flow rate does not change for the power uprate. Additionally, groundwater is not used in current plant operations; therefore, there will be no additional impacts to onsite groundwater use as a result of the proposed action. The NRC staff concludes that the power uprate will not have a significant impact on water usage at Seabrook.
Thermal Discharge:
The licensee indicates that, at uprated power conditions, with normal CWS flow, the circulating water outlet temperature will increase approximately 2.2 degrees Fahrenheit from the temperature associated with the current power level. However, the maximum CWS outlet temperature associated with the proposed action will continue to be within system design parameters.
The licensee evaluated the thermal impact associated with the power uprate relative to the Seabrook National Pollutant Discharge Elimination System (NPDES) permit. The New Hampshire Office of Ecosystem Protection issued NPDES Permit No. NH0020338 to the licensee for operation of Seabrook. The permit was last renewed on April 1, 2002. The NPDES permit specifies that Seabrook shall not cause a monthly mean temperature rise of more than 5 degrees Fahrenheit within 300 feet of the submerged diffuser in the direction of discharge. Historical data indicates that maximum monthly mean temperatures have been within all NPDES permit parameters. Projected maximum monthly mean temperatures predicted to occur in uprated conditions will continue to be below specified permit limits and bounded by the impacts previously evaluated in the FES. Therefore, the NRC staff concludes that there are no significant impacts from the increased thermal discharge to the Atlantic Ocean as a result of the proposed action.
Noise Evaluation:
The noise effects due to operation of Seabrook at uprated power conditions were reviewed. The power uprate does not require any new motors or pumps. In addition, the turbine and the reactor building supply and exhaust fans will continue to operate at current speeds, and the associated noise levels will also be unaffected by uprated power operations.
Consideration of other features affected by the power uprate did not reveal any new and significant sources of noise that would be expected to be noticeable at the site boundary.
Therefore, the NRC staff concludes that the noise impacts of the proposed action are bounded by the impacts previously analyzed in the FES.
The non-radiological environmental impacts related to the proposed power uprate at Seabrook have been reviewed and there are no adverse impacts or significant changes required to the current NPDES Permit or other plant administrative limits. No changes to land use would result from the proposed action, and the proposed action does not involve any historic sites. Therefore, no new or different types of non-radiological environmental impacts are expected than those previously considered in the FES.
Summary:
The NRC has completed its evaluation of the proposed action and concludes that there are no significant environmental impacts associated with the proposed action.
The details of the staffs safety evaluation will be provided in the license amendment that will be issued as part of the letter to the licensee approving the license amendment.
The proposed action will not significantly increase the probability or consequences of accidents. No changes are being made in the types of effluents that may be released off site.
There is no significant increase in occupational or public radiation exposure. Therefore, there are no significant radiological environmental impacts associated with the proposed action.
With regard to potential non-radiological impacts, the proposed action does not have a potential to affect any historic sites. It has a small affect on non-radiological plant effluents and has no other environmental impact. Therefore, there are no significant non-radiological environmental impacts associated with the proposed action.
Accordingly, the NRC concludes that there are no significant environmental impacts associated with the proposed action.
Environmental Impacts of the Alternatives to the Proposed Action:
As an alternative to the proposed action, the staff considered denial of the proposed action (i.e., the no-action alternative). Denial of the application would result in no change in current environmental impacts. The environmental impacts of the proposed action and the alternative action are similar.
Alternative Use of Resources:
The action does not involve the use of any different resource than those previously considered in the FES for Seabrook, NUREG-0895, dated December 1982.
Agencies and Persons Consulted:
On October 18, 2004, the staff consulted with the New Hampshire State official, Michael Nawoj of the New Hampshire Office of Emergency Management, and with the Massachusetts State official, James Muckerheide of the Massachusetts Emergency Management Agency, regarding the environmental impact of the proposed action. The State officials had no comments.
FINDING OF NO SIGNIFICANT IMPACT On the basis of the environmental assessment, the NRC concludes that the proposed action will not have a significant effect on the quality of the human environment. Accordingly, the NRC has determined not to prepare an environmental impact statement for the proposed action.
For further details with respect to the proposed action, see the licensees letter dated March 17, 2004, as supplemented by a second letter dated March 17, 2004, and letters dated April 1, May 26, September 13 (two letters), and October 12, 2004. Documents may be examined, and/or copied for a fee, at the NRCs Public Document Room (PDR), located at One White Flint North, Public File Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible electronically from the Agencywide Documents Access and Management System (ADAMS) Public Electronic Reading Room on the Internet at the NRC Web site, http://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS, should contact the NRC PDR Reference staff by telephone at 1-800-397-4209 or 301-415-4737, or by e-mail to pdr@nrc.gov. (Note: Public access to ADAMS has been temporarily suspended so that security reviews of publicly available documents may be performed and potentially sensitive information removed. Please check the NRC Web site for updates on the resumption of ADAMS access.)
Dated at Rockville, Maryland, this 8th day of December 2004.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Darrell J. Roberts, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation