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 Issue dateTitle
ML22131A1205 May 20221 to Updated Final Safety Analysis Report, Chapter 4, Reactor
ML20323A12022 October 2020Rev. 20 to Updated Final Safety Analysis Report, Chapter 4, Reactor
SBK-L-19138, Radiological Emergency Plan (Ssrep), Revision 7631 December 2019Radiological Emergency Plan (Ssrep), Revision 76
ML17310A41027 October 2017Seabrook Station Revision 18 to Updated Final Safety Analysis Report, Chapter 4, Reactor
SBK-L-17131, Radiological Emergency Plan (Ssrep), Revisions 72, 73 and Er 1.1, Classification of Emergencies, Revision 589 August 2017Radiological Emergency Plan (Ssrep), Revisions 72, 73 and Er 1.1, Classification of Emergencies, Revision 58
SBK-L-16196, Response to Request for Supplemental Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive...15 December 2016Response to Request for Supplemental Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive...
ML16147A18929 April 2016Revision 17 to Updated Final Safety Analysis Report, Chapter 4 - Reactor
ML16068A13527 February 2016Attachment 3 - Clean Copy of Seabrook Emergency Action Levels - Initiating Conditions, Threshold Values and Basis
ML14317A60421 October 2014Seabrook Station Updated Final Safety Analysis Report, Revision 16, Chapter 4, Reactor
ML13212A06924 July 2014Issuance of Amendment Regarding the Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
ML13196A42115 July 2013NRC Staff Answer to Motion for Summary Disposition of Contention 4B - Attachment 4B-E
SBK-L-13071, License Amendment Request 13-0328 May 2013License Amendment Request 13-03
ML13134A08026 April 2013Updated Final Safety Analysis Report, Revision 15, Chapter 4 - Reactor
SBK-L-12052, Submittal of Changes to Technical Specification Bases16 February 2012Submittal of Changes to Technical Specification Bases
SBK-L-11069, Response to Request for Additional Information - Set 12 and Associated License Renewal Application Changes22 April 2011Response to Request for Additional Information - Set 12 and Associated License Renewal Application Changes
SBK-L-09269, Submittal of Changes to Technical Specification Bases30 December 2009Submittal of Changes to Technical Specification Bases
ML0913304783 November 2008Seabrook - Updated Final Safety Analysis Report, Revision 12, Chapter 4, Reactor
ML0806704197 March 2008CDBI Findings
SBK-L-06227, Enclosure 3 to Fple Letter SBK-L-06227 - Ealdbd, Rev a, Seabrook Emergency Action Level Design Basis Document17 October 2007Enclosure 3 to Fple Letter SBK-L-06227 - Ealdbd, Rev a, Seabrook Emergency Action Level Design Basis Document
ML07311041017 October 2007Enclosure 2 to Fple Letter SBK-L-06227 - Emergency Initiating Condition Matrix, Modes 1, 2, 3, & 4
ML07239019023 August 2007Tech Spec Pages for Amendment 116 Technical Specification Task Force (TSTF)-449, Steam Generator Tube Integrity.
ML07088028628 March 2007Technical Specifications, Issuance of Amendment Regarding TSTF -449 Steam Generator Tube Integrity TAC No. MD0696
SBK-L-06059, License Amendment Request 06-03 Application for Amendment to Technical Specifications for Miscellaneous Changes.7 August 2006License Amendment Request 06-03 Application for Amendment to Technical Specifications for Miscellaneous Changes.
SBK-L-06065, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process.28 April 2006Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process.
SBK-L-04127, Response to Request for Additional Information Regarding License Amendment Request 04-0816 December 2004Response to Request for Additional Information Regarding License Amendment Request 04-08
SBK-L-04050, Submittal of Changes to the Plant Technical Specification Bases2 September 2004Submittal of Changes to the Plant Technical Specification Bases
ML02294002411 October 2002License Amendment Request 02-04, Revision to TS Associated with Pressure/Temperature Curves & Low Temperature Overpressure Protection Limits
ML0212601482 May 2002TS Pages Amendment 83
ML02057011821 February 2002License Amendment Request 02-01 for Seabrook Station, Relocation of Certain Engineered Safety Features Pump Values from Technical Specifications to the Technical Requirements Manual - Request 1
Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick5 May 1999Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick
NRC Generic Letter 1998-0228 May 1998NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition
Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown5 December 1997Recent Events Involving Reactor Coolant System Inventory Control During Shutdown
Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown11 December 1996Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown
Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power22 October 1996Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves5 August 1996Unexpected Opening of Multiple Safety Relief Valves
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown18 June 1996Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel18 January 1996Partial Bypass of Shutdown Cooling Flow from Reactor Vessel
Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 115 July 1994Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System24 May 1994Undetected Accumulation of Gas in Reactor Coolant System
ML20134B49316 February 1994Forwards Updated Briefing Package for Visit by Util Officials W/Nrc Chairman,Commission,Edo,Director OI & Director Oe.Requests Replacement of Encls 1 & 2 in 940215 Package,Retaining Supporting Attachment 1 Documentation
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications26 November 1993Potential Problems with BWR Level Instrumentation Backfill Modifications
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels10 August 1993Thermal Stratification of Water in BWR Reactor Vessels
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization8 April 1993Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization
NRC Generic Letter 1992-0419 August 1992NRC Generic Letter 1992-004 - Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(F)
Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown25 February 1992Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown
Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units23 March 1990Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units
ML19324G67915 March 1990Provides Info in Response to late-filed Allegations,Per 900314 Telcon
ML20012E16030 September 1989Evaluation of Seabrook Station.
ML20235E93321 September 1987Forwards Response to Request for Info Re Generic Ltr 87-12, Loss of RHR While RCS Partially Filled. Control Room Reactor Vessel Level Indication Only Effective After Reactor Vessel Adequately Vented
ML20237G74931 July 1987Risk Mgt Actions to Assure Containment Effectiveness at Seabrook Station
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